IR 05000395/1988017

Insp Rept 50-395/88-17 on 880801-31.Violations Noted.Major Areas Inspected:Unresolved Items,Monthly Surveillance & Maint Observations,Operational Safety Verification,Esf Sys Walkdown & Onsite Followup of Events

ML20155A875
Person / Time
Site:	Summer
Issue date:	09/15/1988
From:	Dance H, Hopkins P, Prevatte R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20155A851	List: ML20155A848 ML20155A862 ML20155A875
References
50-395-88-17, NUDOCS 8810060107
Download: ML20155A875 (8)

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/* % UNITED STATES 3 .g NUCLEAR REGULAYORY COMMISSION o * REGION 11

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[ 101 MARIETTA ST., e . . , e *, AYLANTA GEORGIA 30323 Report No.: 50-395/88-17 Licensee: South Carolina Electric and Gas Company Columbia, SC 29218 Docket No.: 50-395 License No.: NPF-12 Facility Name: V. C. Summer Inspection Conducted: August 1 - 31, 1988 Inspector': I

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/ Richard L. Prevatte Oate Signed (i Ib Mefl66 perry C. Hopkins Date Signed Accompanying Per nnelp Stevep J. Vias (August 22 - 26, 1988)

Approved by: 6' b d+v' - - _f TN H6gh C.6 Dance, Sect n Chief 0 te igned Division of Reactor Projects i

SUMMARY Scope: This routine, announced inspection was conducted by the resident

'nspectors onsite, in the areas of unresolved items, monthly surveillance observations, monthly maintenance observation, operational safety verification, f engineered safety features system walkdown, onsite followup of events and

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subsequent written reports, action on previous inspection findings, design, design changes and modifications, and other areas.

I Results: The licensee's periodic Jerformance of STP's has resulted in some temporary procedure chanJes and procedure revisions. Review by procedure writing groups appears to satisfy procedure resiew requirements. Too many 1 changes to a procedure without reprint and study by those who perform STP's could load to confusion and/or errors by personnel who perform test procedure With tho upcoming outage scheduled for September 16, 1988, there appears to have been considerable cooperative ef forts by the several discipline groups to

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produce an outtae schedule of significant detai Within the areas inspected, the following violation was identified:

- Failure to follow procedures, paragraph One unrosolved item was identified involving steam path yielding potential for postulated steam breaks, paragraph 7 G810060107 080916 PDR ADOCK0500g5

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REPORT DETAILS Persons Contacted Licensee Employees

• Baohr, Manager, Chemistry and Health Physics K. Beale, Manager, Nuclear Protection Services

• 0. Bradham, Vice President, Nuclear Operations C. Bowman, Manager, Scheduling and Modifications M. Browne, General Manager, Station Support W. Higgins, Supervisor, Regulatory Compliance S. Hunt, Manager, Quality Systems

• A. Koon, Manager, Nuclear Licensing

• G. Moffatt, Manager, Maintenance Services D. Moore, General Manager, Engineering Services

• K. Nettles, General Manager, Nuclear Safety C. Price, Manager, Technical Oversite J. Shepp, Associate Manager, Operations

• J. Skolds, General Manager, Nuclear Plant Operations

• G. Soult, General Manager, Operations and Maintenance G. Taylor, Manager, Operations D. Warner, Manager, Core Engineering and Nuclear Computer Services

• M. Williams, General Manager, Nuclear Services K. Woodward, Manager, Nuclear Operations Education and Training NRC Resident Inspectors

• P. Hopkins, Resident Inspector R. Prevatte, Senior Resident Inspector S. Vin , Project Manager Other licensee employees contacted included engineers, technicians, operators, mechanics, security force members, and office personne "Attended exit interview Acronyms and initialisms used throughout this report are listed in the last paragrap . Unresolved Item **

See paragraph 7a for a unresolved item identified in this repor "

Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve violations or deviation . .

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2 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 requirements. The inspectors observed portions of 13 selected surveillance tests including all aspects of the Steam Generator "A" Steam Pressure (PT 474) Operability Test, (STP 303.005).

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 TS requirements, test discrepancies were rectified, and the systems were properly returned to servic During this inspection period, personnel in general, who performed the surveillance procedures were knowledgeable and appeared to have familiarized themselves with the procedures prior to the performance of a particular surveillance procedur Coordination and communications between the several disciplines required to perform STP's were adequat Parts, components, test equipment or materials used by test personnel during scheduled surveillance testing activities were found to be properly documented on the associated implementing work requests and the STP' No violations or deviations were identifie . Monthly Maintenance Observation (62703)

The inspectors observed mair.tenance 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 personne 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 in whole or in part:

MWR 8901084 Investigate and repair steam generator "A" feedwater regulator valve PMTS P0109921 SWS "B" train flow operational testing MWR 8801026 Repair switch on MCB for the high pressure turbine to the main steam drain valve PMTS 98203 Repair auxiliary building motor control center switchgear room cooling fan motor (XFN0132-M0)

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PMTS 102296 Repair relief damper equipment in room 435 (XDP0234A)

PMTS 102276 Inspect and repair control room vent control damper (XDP0021A)

PMTS 102292 Repair equipment area relief air damper (XDP0133A)

PMTS 105581 Repair and calibrate circuit breaker feeder for heat tracing (XPC2009)

PMTS 108702 Inspect and replace spare feeder breaker (X5W1DA2)

MWR 8810218 Repair flat washers on intermediate range instrument drawer KWR 8700053 Repair spool piece above support SFH0044 by replacing with new gaskets PMTS 103912 Check and repair spent fuel pit bridge crane PMTS 103961 Lubricate spend feel pit bridge crane PMTS 103963 Inspect spent fuel pit bridge crane for operation KdR 8801249 Investigate and repair feedwater regulator valve (IFV00478)

MAR 88 WOO 37 Install RUSKA gauges on feedwater system to test for moisture carry-over KdR 20797005 Perform circuit termination for plant surveillance system MWR 8800836 Repair fau'ty limit switch on loop "A" component cooling pump "C" Through observation and research conducted during this inspection it has been determined that maintenance activities have been performed per work request instructions and applicable procedure No violations or deviations were identifie . 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 annunciator 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

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equipment, the control of maintenance and surveillance activities in progress, the implementation of radiatinn protective controls and the physical security plan. Tours were conducted during normal and random off hour period In general, the operating crews were observed to be making good use of their time, when not occupied with the normal operating routine. They were observed making needed procedure changes, reviewing procedures, and conducting on-the-job training for those standing watch under instructio Operations watch standing activities and the composition of control room logs was being accomplished in Accordance with the requirements of the controlling procedures and directive 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 Component Cooling Water Syste The inspectnrs confirmed that the licensee's system lineup procedures matched plant drawings and the as-built configuratio 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, et The inspectors verified thit 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 indication Several deficiencies were identified, such as equipment tags missing, oil leaking from limitorques and valves needing some type of preservatio Responsiveness by operations to these items was prompt and positiv No violatiors or deviations were identifie . Onsite Followup of Events and Subsequent Written Reports (92700, 93702) On June 7,1988, with the plant in mode 3 the licensee was notified by the architect engineer for V. C. Summer Nuclear Station that a design defect may yield the potential for steam propagation, which could affect the safe shutdown of the plant under certain postulated steam event Direct steam paths through floor penetrations and more tortuous propagational paths were identified. Upon verification of the potential problem the licensee changed operational modes from mode 3 to mode 4 The licensee opened several interior plant doors to allow for the relief of pressure build-ups. One door was sealed to prevent moisture intrusion in the event of the postulated steam brea .

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The licensee is performing further evaluations of this potential problem to insure that adequate corrective actions are in place for short and long term operation For furthee information see LER 88-008, dated July 7, 1988. This is an unresolved item, steam line rupture with potential to affect safe shutdown, 88-17-0 The inspectors reviewed the following. LER's and SPR's to ascertain whether the licensee's review, corrective action and report of the identified event or deficiency was in conformance with regulatory requirements, TS, license conditions, and licensee procedures and control Based upon this review the following items are close LER 87-11 Lots of 7.2 kV switchgear due to degraded voltage SPR 88-006 Failure of diesel fire pump to start on valid test signal SPR 86-011 keeperability of the meteorological ir.strumentation No vinlations or deviations were identifie . Action on Previous Inspection Findings (92701, 92702)

The inspectors further reviewed the July 26, 1988 reactor trip from 100*;

power, while SSPS was being tested. Subsequent to the June 1, 1988 reactor trip, while performing an SSPS logic test, the licensee made changes to STP 345.074, SSPS actuations logic and master relay test, for train "B", to insure that the breaker would be closed locally instead of from the MC Personnel failed to follow the procedure in that the breaker was closed from the MCB inst ad of locally at the RTB as specified. The solid state protection system actuation logic and master relay test for train B, STP 345.074, was initiated and channel "B" was placed in test at approximately 9:00 a.m., on July 26, 1988. A reactor trip occurred at 9:24 a.m. At approximately 4:30 p.m. , a relief shif t supervisor entered the control room and discovered that SSPS train "B" was still in tes The channel was returned to normal at approximately 5:30 STP 345.074, precaution step 3.9 limits the time that a channel may be bypassed for testing to two hours. The procedure was not followed in that operations allowed the SSPS train "B" to remain in bypass for over eight hours. During the time "B" train was in test no protection signal could have been generated by that channel. Step 3.10 of the above procedure also requires that if the test was terminated prior to

ompletion it must be returned to norma This is an additional example of the above violation for failure to follow procedures, 88-17-01. See. Report No. 50-395/88-14 and LER 88-009 for further information, 9. Design, Design Changes and Modifications (37700)

The inspectors reviewed four design changes,1.'sted belnw not previously approved by NRR, to assure that the changes had been reviewed and approved

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in accordance with the Technical Specifications (TS) and 10 CFR 50.5 During the review, the inspectors verified (1) that the design changes ,

were reviewed and approved in accordance with TS and established QA/QC controls, (2) that design changes were controlled by established procedures, (3) that the licensee conducted a review and evaluation of test results and that these test results were within previously established acceptance criteria and that any test deviations tere resolved and necessary retesting was accomplished as appropriate, (4) that operating procedure modifications were made and approved in accordance i

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with TS, and (5) that as-built drawings were changed to reflect the modifications. The inspectors ot> served (1) that change activities were conducted in accordance with the appropriate specifications, drawings, and other requirements, (2) that acceptance and startup testing of modifi-cations were conducted in accordance with technically adequate and approved procedures, and (3) that appropriate controls were implemented, (e.g. , firewatch, portable fire fighting equipment, welding and cutting permit, etc.). Additionally, the inspectors reviewed the outstanding facility change requests (FCR's) and determined that an excessive backlog was not developing. Design changes reviewed were:

M F 21097 Installed spare pump concept for swing systems No violations or deviations were identifie . Other Areas Other activities related to the inspection program are noted:  ; The Assistant Director for Region II Reactnr Projects, the Director, Reactor Projects Directorate 11-1 and the Region II Deputy Director i for Reactor Projects, visited and toured the plant NTC and EOF on August 3, 198 The Senior Resident Inspector assisted Region II in conducting an OPA of the Vogtle Nuclear Plant during the week of August 8 and d , 198 The Regional Project Engineer for V. C. Sumner assisted the Resident f Inspectors during the week of August 22, 198 . Exit Interview (30703)

The inspectirn scope and findings were summarized on August 31, 1988, with !

those persons indicated in paragraph 1 above. The inspectors described i the areas inspected and discussed the inspection findings. No dissenting ,

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comments were received from the license The licensee did not identify as proprietary any of the ' materials provided to or reviewed by the inspectors during the inspectio Item Number Description and Reference 88-17-01 Violation - Failure to Follow Procedures, paragraph URI - Steam Line Rupture with Potential to !

Affect Safe Shutdown, paragraph . Acrenyms and Initialisms EOF Emergency Operating Facility ESF Engineered Safety Feature LER Licensee Event Report MCB Main Control Board MWR Maintenance Work Request NRC Nuclear Regulatory Commission NRR Nuclear Reactor Regulation NTC Nuclear Training Center OPA Operational Performance Assessment PMTS Preventative Maintenance Task Sheet QA Quality Assurance RTB Reactor Trip Breaker SPR Special Procedures Report SSPS Solid State Protection System STP Surveillance Test Procedures SWS Service Water System TS Technical Specifications URI Unresolved Item

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