IR 05000395/1988005

Insp Rept 50-395/88-05 on 880201-29.No Violations or Deviations Noted.Major Areas Inspected:Monthly Surveillance Observations,Monthly Maint Observation,Operational Safety Verification,Esf Sys Walkdown & Physical Security

ML20148F243
Person / Time
Site:	Summer
Issue date:	03/14/1988
From:	Dance H, Hopkins P, Prevatte R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20148F231	List: IR 05000395/1988005 ML20148F227
References
50-395-88-05, 50-395-88-5, NUDOCS 8803280099
Download: ML20148F243 (6)

Text

{{#Wiki_filter:-- . ~ . ~ . . . . - - - - . ~ .. . . _ _ - -

km REG UNIVED STATES

. o -

NUCLEAR REGULATORY COMMISSION

.[[T I n    REGloN il 3  y   101 MARIETTA STREET, *  's   ATL ANTA, GEORGI A 30323     l
\ ....../          l Report No.:  50-395/88-05 Licensee: South Carolina Electric and Gas Company Columbia, SC 29218 Docket No.:  50-395    License No.:  NPF-12 Facility Name:  V. C. Summer
. Inspection Cond cted:  Februar 1-29, 1988 Inspectors:  it Richard't,e Prevatte'

W"

     '

k 3/ /[ D'a t Signed 49 - opkins

   -
    '

t?+~n '

     /h   __3, lh W
  'Perr/ DatySigned Approved by:  #fh- M Hugh6C. Dance, Section Chief 3Orte[/Signed
        [ [

Division of Reactor Projects SUMMARY Scope: This routine, announced inspection was conducted by the resident inspectors onsite, in the areas of monthly . surveillance observations, monthly maintenance observation, operational safety verification, engineered safety features system walkdown, radiological protection, physical security, and onsite followup of events and subsequent written report Results: No violations or deviations were identifie GG0315 5 PDR ADOCK 0500 Q

, _ _ . - __ _ - - - -
  -

_ _ _ _ _. _ _ _ _ _ ,

  .- .. _ .. - -.  . . .. _
. .
,
.
 .

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

*0. Bracham, Director, Nuclear Plant Operations
*D. Moore, General Manager, Engineering Services M. Williams, General Manager, Nuclear Services K. Nettles, General Manager, Nuclear Safety
*J. Skolds, General Manager, Station Operations
*M. Browne, General Manager, Station Support
*G. Moffatt, Manager, Maintenance Services
*G. Soult, Manager, Operations A. Koon, Manager, Nuclear Licensing C. Bowman, Manager, Scheduling and Modifications K. Woodward, Manager, Nuclear Operations Education and Training W. Baehr, Manager, Chemistry and Health Physics
*S. Hunt, Menager, Quality Systems    .

K. Beale, Manager, Nuclear Protection Services j C. Price, Manager, Technical Oversite D. Warner, Manager, Core Engineering and Nuclear Computer Services

*J. Shepp, Associate Manager, Operations   l W. Higgins, Supervisor, Regulatory Compliance NRC Resident Inspectors R. Prevatte, Senior Resident Inspector
*P. Hopkins, Resident Inspector Other licensee employees contacted included enginears, technicians, operators, mechanics, security force members, and office personne l
* Attended exit interview Exit Interview (30702,30703)

The inspection scope and findings were summarized on March 1,1988, with those persons indicated in paragraph 1 above. The inspectors described the areas inspected and discussed the inspection finding The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspectors during the inspectio . 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 21 selected surveillance tests including all aspects of the Reactor u

     ,_ __ _ _ _ .
. .

0 *

Building Close Out Inspection. 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 servic 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 1 adequate to control the activity, and that these activities were accomplished l I by qualified personne The inspectors independently verified that

      !

equipment was properly tested before being returned to servic 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 syste The following specific maintenance activities were observed: MWR 8700146 Perform inspection of welds on spent fuel pool heat exchanger per non-conformance notice 2836 PMTS P0092014 Perform inspection and cleaning of electrical breaker XSW1DAl-07D MWR 88I0049 Repair and recalibrate power range N-42 detector "B" l output MWR 8800238 Investigate and repair breaker and damage in wiring for generator field exciter control cubicle MWR 88M0132 Adjust and add packing as necessary on the feedwater isolation valve (IFV00478 FW) PMTS P0091765 Inspect, clean, repair and test as necessary circuit breakers on the charcoal exchanger (XFN0019C) MWR 88E0035 Change out and relabel conduit on the main steam header "C" power relief valve 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 - _ _ - . _ - . . - . --

      .
-

.

. .

3 I 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 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 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 ar.d random off-hour periods, On February 16, 1988, at 11:30 p.m. with the plant at 100 percent power a reactor trip occurre At approximately 1:00 p.m., February 16, 1988 power range channel, N-42, was declared inoperable during the performance of a Surveillance Test Procedure (STP) because the detection instrumentation was out of TS requirement The bi-stables associated with the power range channel, N-42, was placed I in the trip condition within one hour as required by TS 3.3.1, action ! item 2 At 11:30 p.m. the licensee pr '",ed a quadrant power tilt ratio (STP 108.001). as required ' 3.3.1, a; tion item 2C and TS 4.2.4.2. While performin- - Li3.001 on the power range channel N-44, a negative rate trir canal was ganerated when the test equipment jack was placed in contact with the test point on the printed circuit boar The terminal post on the meter test board consists of a brass nut with a bolt and washer on each side, with the washer establishing continuity to the printed circuitr Investigation of this design shows that it is inherently subject to mechanical loosening. Further investigation showed that three of the power range drawers had this deficiency. When the test equipment jack was placed in contact with the test point, the loose nut on the back side allowed the washer to break contact with the printed circuitry establishing an open circuit and resulting in a negative rate trip signal. This signal, along with the N-42 trip signal, (established by the tripped cy-stable), satisfied the 2/4 coincidence resulting in a negative rate reactor tri Approximately 15 minutes after the trip an electrical fire was reported in the main generator exciter cubicle in the turbine building. The reactor operator then noted that the exciter breaker, which had previously been opened, had reclosed. Attempts to open the breaker at the main control board and locally were unsuccessful. The operators and fire brigade members extinguished the fire locally with CO2. While applying the CO2 the breaker opene _ _ _ . _

_ _ _ -- - _______ ..

. .
*

l

Other safety equipment functioned as designed. The licensee is currently investigating these items and the-failure of the generator exciter breaker. A LER, 88-02, is being prepared on the above event 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 Service Water System. The inspectors 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 that valves, including instrumentation isolation valves, were in proper position, power was available, and valves were locked as appropriat The inspectcrs compared both local and remote position indications. A list of minor deficiencies such as missing tags, broken position indicator glass and procedural typographical errors were identified to the licensee. These deficiencies have been correcte No violations or deviations were identifie . Radiological Protection (71709) The inspectors, as a part of other routine inspections and work activities inside the radiation controlled area (RCA) of the plant, observed and inspected selected areas of the licensee radiological program and i control , The inspectors additionally selected a Radiation Work Permit (RWP),  ; Calibration of "B" steam generator level transmitter, 88-0075, and 1 verified that the RWP contained the information required by the licensee's l procedures to perform the work in a safe manner under controlled  ! conditions. The inspectors observed portions of the activities and health i physics coverage provided under this RW No violations or deviations we e identifie . Physical Security (71881) i The inspectors verified that the security organization shift manning met j the requirements of the licensee physical security pla Special i inspections and routine observations conducted during the performance of l

      '

other duties and inspections verified that installed access control equipment, barriers and systems were maintained operational and utilized ; to control personnel, packages and equipment access to protected'and vital i areas of the plan Positive control is maintained over authorized visitor Compensatory action is taken on each occasion when search equipment, alarm systems or protective barriers become inoperable. Plant . )

 - -.--  . ._. . _ . . - .- . ~ . - . . ..- -
       --- ..
. . . .

e O

 ,

areas are adequately illuminated and adequate patrols are maintained. The licensee's security procedures are enforced. Installed detection .and assessment equipment and systems are well maintained and properly used by i the security forc No violations or deviations were identifie . Onsite Followup of Events and Subsequent Written Reports (92700,93713,93702) The inspectors reviewed the following 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 control Based upon this review the following items are ' close , SPR 85-005 Appendix R deficiency for source range instrumentation cables j SPR 86-012 Main steam line process radiation monitor RMG19A No violations or deviations were identifie I a FI ie,, - r ~ -,,,,.s.w~ -+- -.-- n,-, ., ,., - - , - r>-r s - -,- , v o ~ + }}