IR 05000395/1986019

Insp Rept 50-395/86-19 on 861001-31.No Violations or Deviations Noted.Major Areas Inspected:Licensee Action on Previous Insp Findings & Onsite Followup of Events & Subsequent Written Repts

ML20214G028
Person / Time
Site:	Summer
Issue date:	11/05/1986
From:	Dance H, Hopkins P, Prevatte R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20214G010	List: IR 05000395/1986019 ML20214G008
References
50-395-86-19, NUDOCS 8611250528
Download: ML20214G028 (6)

Text

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Sa Krog UNtTED STATES

/ o NUCLEAR REGULATORY COMMISSION

[*' REGloN 11 g j 101 MARIETTA STREET. * 's ATLANTA, GEORGI A 30323 s.,*****/

Report No.: 50-395/86-19 ,

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: October 1-31, 1986 Inspectors: %' C Richar# L. PreVatte a%c !E '

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Date S'igned

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Date'51gned Approved by: n ( d,w < // 4 d Hugh 't. Dance,\ Section Chief Dat6 Signed 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 and. operational safety verification.

l Results: No violations or deviations were identified.

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i 8611250528 861114 PDR ADOCK 05000395 G PDR

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T REPORT DETAILS

, 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

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M. Browne, Group Manager, Technical and Support Services l 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,

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operators, mechanics, security force members, and office personne . Exit Interview (30702, 30703)

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The inspection scope and findings were summarized on October 31, 1986, with

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those persons indicated in paragraph 1 above. The inspector 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 l

inspectors during the inspectio . Licensee Action on Previous Inspection Findings (92701, 92702)

(0 pen) Unresolved Item 86-15-02, Limitorque wiring qualification. This item was originally identified by the licensee and discussed in paragraph 11 of Inspection Report 86-15. Since initial identification, the following events related to this problem have occurre On August 19 and 22, 1986, Region II's Atlanta based personnel held discussions with South Carolina Electric and Gas Company (SCE&G) staff members. These discussions addressed SCE&G's actions pertaining to IN 86-03 and -IN 83-72 concerning the environmental qualification of Limitorque Valve Motor Operators (VMOs) internal wirin The licensee submitted a letter dated August 26, 1986, which gives the status of the Limitorque VM0 environmental qualification and also provides a justification for continued operation (JCO).

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During an inspection on August 20, 1986, 19 valves were checked. SCE&G identified six Limitorque VM0s out of the 19 that had questionable internal wiring. The licensee replaced the questionable wiring with environmentally qualified wirin The inspection and replacement of the remaining Limitorque VM0s, that can be worked during power operation, will be completed by September 30, 1986. The remaining Limitorque VMOs will be inspected and corrective action will be completed, if necessary, during the next outage of sufficient duration, which is planned for the second quarter of 1987. Since there are some questions involving interpretation of 10 CFR 50.49 and the November 30, 1985 deadline, this will remain an unresolved item identified as 395/86-15-02, Limitorque Wiring Qualificatio (Closed) Inspector Followup Item 84-11-01, Deletion of valves from local leak rate (LLR) Type C test based on submitted Technical Specification (TS)

change and 10 CFR 50.59 review. This item addressed a concern with premature deletion of LLR Type C test valves from TS and the Inservice Inspection Program. A review of this item by the inspector indicates that the identified valves, XVG-8884 and XVG-8885, are still in TS Table 3.6-1 and the Inservice Inspection Program as identified in General Test Procedure (GTP) 302, Revision 1, Attachment 1. A review of the current surveillance test procedure, for Type "C" Local Leak Rate Testing, STP-115.033, also indicates that the applicable surveillances are still scheduled and performed. The additional concern on valve control during the performance of inservice inspection and local leak rate testing appear to be adequately addressed for the two above valves in STP-115.00 This procedure additionally requires independent verification of correct valve position during the performance of their inservice and local leak rate testing. This item is close (Closed) Inspector Followup Item 86-12-02, Error in 5 Cal program, was closed in Report 86-16. An administrative error, in that report, identified this item as 86-12-03. Licensee Identified Violation 86-12-03, was closed in report 86-16, under unresolved item 86-09-01. Both of the items are close (Closed) Inspector Followup Item 86-06-03, Incorrect load listing in the general maintenance procedure. This item involved a reactor trip that resulted frcm maintenance personnel deenergizing a power supply circuit to the kidney loop condensate polishers, which resulted in a loss of condensate flow. The above problems were the result of an error in the electrical feeder list of power supplies to electrical equipment. The licensee has performed a verification of the electrical feeder list and corrected identified errors. A review of this list by the inspector indicates that this problem has been correcte This item is close (Closed) Violation 86-06-01, Loop B component cooling and service water pumps out of service for a period greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, due to incorrect electrical alignmen The licensee provided written responses to this violation in letters to Inspection and Enforcement Headquarters dated May 15, May 23, and October 17, 1986. The inspector reviewed the licensee's

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response and corrective action. They appear to be adequate to prevent recurrence. This item is close . Monthly Surveillance Observation (61726)

The inspectors observed surveillance activities of safety related systams 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 test involving safety related system 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 servic The following specific surveillance activities were observed:

STP 134.001 Shutdown margin calculation STP 125.002 Diesel generator operability test STP 105.016 Charging pump and diesel generator slave relay testing STP 109.001 Reactor building closecut inspection STP 115.032 Reactor building air lock door seal leak +.est l STP 114.002 Operational leakage test STP 302.038 NIS power range (N41) operational test STP 128.065 Ventilation fire damper inspection STP 302.002 Delta temperature - Tavg protection loop 2

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PMST P0069970 Testing and balancing of control room outside intake air flow transmitter STP 134.001 Shutdown margin verification l STP 360.032 Control room supply air atmospheric radiation monitor i (RMA-1) channel operational test

STP 303.008 Steam generator "A" steam pressure transmitter j operational test i

l STP 302.041 NIS power range (N44) operational test

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No violations or deviations were identified.

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! Monthly Maintenance Observation (62703)

The inspectors observed maintenance activities of safety related systems and components to ascertain that these activities were conducted in accordance

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with approved procedures, TS and appropriate industry codes and standard The inspectors also determined that the procedures used were adequate to

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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

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licensee was giving priority to safety related maintenance and a backlog i which might affect its performance was not developing on a given system.

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The following specific maintenance activities were observed:

MWR 8601394 Repair valve diaphragm leak XVD085428 (CS)

MWR 8601397 Repair valve diaphragm leak XVD08542A (CS)

MWR 8601396 Repair valve diaphragm leak XVD085248 (CS)

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MMP 445-006 General maintenance of diaphragm valves l MWR 8601436 Repair manifold valve XVG08073A on loop "A" hot leg

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outlet No violations or deviations were identified.

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 j 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

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printouts and annunciators. Tours of other plant areas were conducted to i

verify equipment operability; control of ignition sources and combustible j 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

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plan. Tours were conducted during normal and random off hour periods.

! On September 8 and 25, 1986, with the plant in Mode 1, the licensee's identified that the hourly fire watch patrols were not performed, in various

! areas, within the time requirement of technical specifications. The cause

of the September 8, 1986 event was the result of inadequate turnover of fire watch patrol duties during shift turnove Because of the inadequate turnover, the 0200 hour0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> fire watch patrol was not performed. The elapsed time between the 0130 hour0.0015 days <br />0.0361 hours <br />2.149471e-4 weeks <br />4.9465e-5 months <br /> and the 0230 hour0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br /> patrol varied from sixty-four to seventy-nine minutes. The cause of the September 25, 1986 event was the

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result of the fire watch patrol's failure to patrol fire areas at 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br /> which were listed on the back side of the page of the fire watch lo Patrols were performed at 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br />, 1630 hours0.0189 days <br />0.453 hours <br />0.0027 weeks <br />6.20215e-4 months <br /> and 1730 hours0.02 days <br />0.481 hours <br />0.00286 weeks <br />6.58265e-4 months <br />. The elapsed time varied from seventy-four to seventy-five minutes. This is contrary to the requirements of TS 3.7.10, which requires the licensee to establish and maintain hourly fire watches for inoperable fire barriers. No citation was issued under the NAC enforcement policy, as this is considered a violation of lesser severity, which was identified and satisfactorily corrected by the license No other 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 Residual Heat Removal System. The inspectors confirmed that the licensee's system lineup procedures matched plant drawings and the as-bailt configura-tion. 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. The inspectors verified that valves, including instrumentation isolation valves, were in proper position, power was available, and valves were locked as appropriat The inspectors compared both local and remote position indication 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 (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 control Based upon this review the following items are closed:

LER 86-07 Reactor building spray pump "B" inadvertently started LER 86-15 Late fire watch patrol SPR 85-018 Isothermal temperature coefficient measurement LER 86-02 Turbine trip / reactor trip due to loss of condensate flow

j SPR 85-006 Appendix R cable tray separation SPR 85-019 Load sequencer malfunction No violations ur deviations were identified, i

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