IR 05000395/1987036

Insp Rept 50-395/87-36 on 871201-880104.No Violations or Deviations Noted.Major Areas Inspected:Licensee Action on Previous Insp Findings,Monthly Surveillance Observation, Operational Safety Verification & IE Bulletin Followup

ML20148T410
Person / Time
Site:	Summer
Issue date:	01/20/1988
From:	Dance H, Hopkins P, Prevatte R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20148T381	List: IR 05000395/1987036
References
50-395-87-36, IEB-87-002, IEB-87-2, NUDOCS 8802030297
Download: ML20148T410 (7)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION

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Clog o REGION ll

_g j 101 MARIETTA STREET, *1 i .c ATL ANTA, GEORGI A 30323

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Report No.: 50-395/87-36 Licensee: South Carolina Electric and Gas Company Columbia, SC 29218 Docket No.: 50-395 License No.: NPF-12 Facility Name: Summer Inspection Condu ed: December 1 - January 4, 1988 Inspectors: ( / 20 7 RichadL.PrgVatte / /Dat 51 ned Perr (Y!

. Hopk' ins (

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' Signed Approved by: v, ( a. #

'Hugh & Dance, Section Chief

/ 70 f'8 Fate 61gned Division of Reactor Projects SUMMARY Scope: This routine, announced inspection was conducted by the resident in*pectors onsite, in the areas of licensee action on previous inspection rindings, monthly surveillance observation, monthly maintenance observation, operational safety verification, ESF system walkdown, onsite followup of events and subsequent written reports, and I.E. bulletin followu Results: No violations or deviations were identifie DR ADOCK O

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REPORT DETAILS Persons Contacted Licensee Employees D. Nauman, Vice President, Nuclear Operations

• 0. Bradham, Director, Nuclear Plant Operations 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

• H. 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 K. Beale, Manager Nuclear Protection Services A. Paglia, Manager Licensing

• W. Higgins, Associate Manager, Regulatory Compliance

• B. Williams, Supervisor, Operations NRC Resident Inspectors

• Prevatte, Senior Resident Inspector

• Hopkins, Resident Inspector Other licensee employees contacted included engineers, technicians, operators, mechanics, security force members, and office personne * Attended exit interview Exit Interview (30702, 30703)

The inspection scope and findings were summarized on January 4, 1987, 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 l reviewed by the inspectors during the inspu tion.

1 Licensee Action on Previous Inspection Findings (92701, 92702)

l l (Closed) IFI 395/85-23-02, Determination of inspection requirements for i seismically designed steel platforms. 1he inspector reviewed licensee l procedures and plans for inspection of seismically designed steel

platforms. The items reviewed included Quality Related Plan No. QRP-5 for l Quality Related Access Steel, Rev. O, dated June 12, 1986 and drawing

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No. 04 4461 E-511-260 Rev. A, dated September 30, 1987, list of quality related access steel associated with QRP-5. Based on this review there are no further questions at this time. This item is close . Monthly Surveillance Observation (61726)

The inspectors observed surveillance activities of safety related systems and components to ascertain that these activities were conducted in accordance with license requirement The inspectors observed portions of selected surveillance tests including all aspects of one major surveillance 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, test discrepancies were rectified, and the systems were properly returned ,to service. The following specific surveillance activities were observed:

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STP 114.002 Operational Leakage Test STP 102.002 Nuclear Instrumentation System Power Range Heat Balance STP 112.002 Reactor Building Spray Pump Test STP 120.002 Turbine Driven Emergency Feedwater Pump Test STP 122.002 Component Cooling Pump Test STP 360.006 Reactor Building Area Radiation Monitor (RM-G7) Operational Test

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STP 506.001 Pressurizer Heater Capacity Test STP 506.002 RCP Undervoltage Unit Trip Actuating Device Operation Test ,

STP 506.003 RCP Underfrequency Unit Trip Actuating Device Operational Test STP 302.030 Steam Generator "C" Steam /Feedwater Flow Instrument Operational Test STP 506.009 Reactor Trip Breaker Shunt and Undervoltage Trip Verification STP 108.001 Quadrant Power Tilt Ratio STP 105.001 Charging / Safety Injection Pump Test No violations or deviations were identifie _ _ _ _ _ _ _

. 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 codes 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:

PMTS P0094095 Perform resistance check on speed switch on the air handling unit "B" supply fan MWR 8701774 Inspect, test and repair / replace molded case circuit breaker on XMC1002Y 13AD MWR 8702070 Repair level switch on the turbine driven emergency feedwater pump (IC502031)

PMTS P0097975 Inspect and resplice wires in termination box for steam generator "A" turbine driven air operated emergency feed pump flow control valve IFV03536EF PMTS P0097977 Inspect and resplice wires in termination box for steam generator "B" turbine driven air operated emergency feed pump flow control valve IFV03546EF PMTS P0097979 Inspect and resplice wires in termination box for steam generator "C" turbine driven air operated emergency feed pump flow control valve IFV03566EF MWR 87E0253 Remove brush recorder used to monitor ambient temperature on and around the 270 relays (voltage relays)

PMTS P0098405 Investigate and repair wiring for accumulator tank sample header isolation valve X0XO9387-SS PMTS P0098296 Perform inspection and repair / replace splices as necessary on purge line isolation valve XVG06057-HR solenoid 20- No violations or deviations were identifie !

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. . Operational Safety Verification (71707)

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 requirement 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 implementation of radiation protective controls and the physical security plan. Tours were conducted during normal and random off hour period No violations or deviations were identifie . 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 Reactor Building Spray System. The inspectors confirmed that the licensee's system lineup procedures matched plant drawings and the as-built configuration. The inspectors looked for equipment conditions and items that might degrade pe"formance (hangers and supports were operable, housekeeping, etc.) and inspected the interiors of electrical and instrumentation cabinets for debris, loose material, jumpers, evidence of rodents, et 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 deficiercies such as missing equipment tags and housekeeping were identifie These items were immediately corrected by the license No violations or deviations were identifie . Onsite Followup of Events and Subsequent Written Reports (92700, 93713, 93702)

The inspectors reviewed the following Licensee Event Reports (LER's) 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 close LER 87-017 Seismic instrumentation setpoints I

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LER 87-022 ESF actuation auto start of motor drum emergency feedwater pump LER 87-025 Environmental qualification of 600 volt taped wiring splices. This item resulted in a special team inspection being conducted in this area by Region II, during the period of October 20-23, 1987. The deficiencies associated with the items discussed in the above LER were identified as violations in report 395/87-30. Corrective actions associated with above items will be tracked as a part of violations 87-30-01 and 87-30-0 No violations or deviations were identifie . I.E. Bulletin Followup (92703)

The inspectors accompanied licensee personnel during the selection of fasteners for testing as required by NRC Compliance Bulletin No. 87-02, Fastener Testing to Determine Conformance with Applicable Material Specifications. The licensee's selection of fastening materials for laboratory testing was not strictly based on usage data but was based on which types were contained in the largest quantities in the warehouse and the types listed in the bulletin with strong NRC interest. A later review of usage data by the licensee indicated that the selected samples were representative of plant usag ,

The samples consisted of 10 safety related fasteners of the following types; A 325, type 2, A 193, grades 87 and B8, A 307, grades A and B, and A 490, type 87. The safety related nuts for these fasteners consisted of A 563, grade A and A 194, type 2H. The 10 non-safety fasteners were A 354, grade BD, A 563, grade B, A 449, A 574, grade 4140, and F 593, alloy 303. The nuts for these fasteners were A 563, grade The above samples were shipped to LAW Engineering Industrial Services, 501 Minuet Lane, Charlotte, NC on December 11, 1987. The testing was completed and the results were returned to the licensee on December 18, 1987. The test results for the safety related fasteners indicated that one A 307, grade B fastener and one A 490 type 1 fastener failed the Rockwell hardness test. The A 307, grade B fastener's average of three readings was 66.3 vice the 69 required minimum. The A 490, type 1 fastener failed the Rockwell C and B hardness tests with an average of chree readings of 22.2 vice 33 and 95.0 on the B scale. One A 325, type 2 fastener failed the chemical analysis with high Carbon of 0.39 vice 0.37 and Boron of less than the 0.0005 required minimum. For the non-safety fasteners one A 574, grade 4140, failed the hardness test with average readings of 30 and 34 on two samples vice the 37 require One F 593 bolt failed the chemical analysis with Nickel reading 7.89 vice the required and Sulfur reading 0.01 vice 0.15 minimum required. An additional F 593 fastener failed the chemical analysis with Nickel reading 7.96 and Sulfur reading 0.01. A third F 593 fastener failed Sulfur with a

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reading of 0.0 A copy of. the test -results were provided to Region II under separate correspondenc The licensee is currently preparing a report on this ite ,

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