IR 05000395/1990018
| ML20055H381 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 07/12/1990 |
| From: | Cantrell F, Modenos L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20055H376 | List: |
| References | |
| 50-395-90-18, NUDOCS 9007260127 | |
| Download: ML20055H381 (6) | |
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UN!TEISTATES $
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' Report No.:e 50-395/90-18
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- Licensee
South Carolina Electric &LGas Company
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Columbia, SC,29218
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' Docket No.':
50-305 -
License.No.:.NPF-12
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- * LFacility Name:~- V.t Cc Summer
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,' 3 Inspection; Conducted:' June;1 30, 1990
.rIns k // ba. M~.owv 7-12-96
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'U g leo P. Modenos Date Signed
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Nf Approved by:
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oyd S. Cantrell, Section Chief
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Reactor Projects.Brarch 1
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SUMMARY
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. Thi's routin'e !1nspection was cor.duchd -byJ the resident inspectors onsite in the
^g; Jareas of monthly' surveillance.. observations, monthly maintenance observation, a
T o operational - safety. verification.. onsite follow-up of 1 written - reports L of-C nonroutine? events. at power reactorEfacilities,- onsite follow-up of-events at
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1 operating. power reactors, action. eniprevious, inspection findings. and. other
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areas., Selected tours were conducted l on backshift or weekenos.. Backshift
Lor weekend tours werel conducted on 12 occessions.
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'The-u' nit wasz o)erated at 100 percent power tr.*9ughout the. reporting period. A
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violation involving failure to follow procedures was identified'(paragraph 6).
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e The < licensee:is investigating thc root cause of this ever.t and'a concern about
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independent' verification:which has been :aJproblem in reent months.-
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90n l June: 25%nd 26; < 1990, Larry Cohen Efrom the Emergency Preparedness (EP)
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$Branchs ; NRRLand, Ann Boland, EG, RII, visited the site to review plans to
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relocate the Emergency Operations Facility (EOF).
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and met with the licensee and
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--resident, inspector, L
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9007260127 900712
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REPORT: DETAILS U
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Persons Contacted
Licensee Employees W. Baehr, Manager, Chemistry and Health Physics
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- C.; Bowman, Manager, Maintenance Services
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0. Bradham, Vice President, Nuclear Operations -
- M. Browne,-Manager,_ Systems Engineering'& Performance
.S. Furstenberg, Associate Manager, Operations
- W.' Higgins, Acting Manager Licensing
- A.LKoon, Acting General Manager, Nuclear Safety
- D. Moore, General Manager Steam Generator Project
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C. Price, Manager, Technical Oversite
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- M. Quinton,' General Manager, Engineering. Services
J. Skolds, General Manager, Nuclear Plant Operations
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- G. -Soult, General. Manager, Operations and Maintenance G. Taylor, Manager, Operations U
D. _ Warner, Manager, Core Engineering and Nuclear Computer E9rvices M. Williams, General Manager,: Administrative & Support Services K. Woodward, Manager,- Nuclear Operations Education snd Training Other licensee employees contacted _ included engineers, technicians,.
operators, mechanics, security force members, and office' personnel.
- Attended exit interview Acronyms and initialisms used throughout this report are listed in the last-paragraph.
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
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.five selected surveillance tests including all aspects of STP 120.001, B EFW Pump Test.
The inspectors 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 service.
No violations or deviations were identified.
3.
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, industry codes and standards.
The inspectors determined that the precedures used were adequate to s
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>V control' the ? activity, Land that these. activities were accomplished by.
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. qualified ' personnel.
The inspectors independently verified that the
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. equipment was properlyftested before ' being' returned to service.-
' Additionally, the inspectors _ reviewed several outstanding. job'. orders to
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1 determine that 'the '. licensee: was giving priority to safety _related M
maintenance = and. notc developing 'a backlog which might affect a. given l
system's performance.
The. following specific maintenancei activities
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'MWR 213600034-Install relay and perform wiring changes per MCN 21360-N 1 X MWR 9001261
. Investigate / troubleshoot valve operation of FW i
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heater.1A drain valve i
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MWR 001094 Repair--leak on blowdown heat exchanger A first stage
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MWR-90D0090-Repair foam blockouts for in..e #142 Rm 12-04 N wall
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PMTS P0133571 Loop calibration of SG B flow transmitter i
PMTS P0134004 Inservice inspection of EFW pump B motor
4-PMTS P0131474.
Electrical inspection of'EFW pump
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t PMTS P0134171.
Inservice _ inspection of FWP area handling unit B
& PMTS P0134027
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-PMTS-P0133398-Se.ci-annual calibration test for flow indicator on K
TDEFW pump
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No violations or-deviations were identified.
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. 4.. - Operational Safety Verifi_ cation (71707)
I The inspectors conducted daily inspections in the following-areas:
control room staffing, access, and operator behavior; operator adherence
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.to ; approved.- procedures, TS, and limiting conditions -for operations;
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examination _ of. panels containing instrumentation and other reactor
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protection system elements to determine that required channels are
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operable; and review oi control room operator logs, operating orders, y
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plant deviation reports, tagout logs, jumper logs, and tags on components
l to verify compliance with approved procedures.
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'The -inspectors conducted weekly inspections in the following areas:
verification of operability of selected-ESF systems by ) valve alignment,
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breaker-positions, condition of equipment or component (s, and operability l
of instrumentation and support items essential to system actuation or
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Plant tours included Lobservation of_ general plant / equipment conditions.
fire protection and' preventative measures, control of activities tin.
progress, radiation protection controls.,- physical security _ controls,l plant housekeeping conditions / cleanliness, and missile-hazards, w
The inspectors conducted biweekly inspections -in the following areas:.
verification review and-.walkdown of safety related tagout(s).in effect;--
' review of -sampling program (e.g.,- primary and secondary coolant samples,-
boric acid tank samples, plant liquid and gaseous samples); observation of:
control: room shift turnover; review of implementation of the plant problem
+t identification sy(s)em;. verification of selected portions of containment:; and verificatio st isolation lineup as required by 10 CFR 19.
Selected tours were conducted or backshifts or weekends.
Inspections included areas:in the cable vaults, vital battery rooms, safeguards areas, emergency switchgear rooms, diesel-generator rooms, control room, auxiliary ^
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building, containment, cable penetration areas, service water intake-structure, and.other general plant areas.
Reactor coolant system leakt rates were reviewed to ensure that detected or suspected leakage from the
- system was -_ recorded, investigated, and evaluated; and that' appropriate :
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Gn a regular basis, R'.iP's were reviewed
' actions ~were taken, if' required.
and specific work activities were monitored to assure -they were being conducted per-the RWP's.
Selected radiation protection instruments were
- periodically checked. and equipment operability-and calibration frequency were verified.
In the: course of monthly activities, the inspectors included a review of-the licensee's physical security program.
The performance -of various shifts of the security force was observed in_ the conduct of daily
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protected and vital areas access ' controls;
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searching of personnel, packages - and vehicles; badge issuance and retrieval; escorting' of visitors; and patrols and compensatory posts.
No-violations or deviations were identified.
5.
Onsite Follow-up of Written Reports of Nonroutine Events at Power Reactor Facilities (92700)
The inspectors' reviewed the following 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
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conditions, and licensee procedures and controls.
. (Closed) SPR 89-009, Diesel Fire Pump inoperable. This special report was
' issued because 'the diesel fire pump was inoperable in excess of seven days
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as referenced-by TS 3.7.9.
A defective cooling water pump rest 0 sed in a failed surveillance test.
The licensee replaced the defective pump and
' system was declared operable after post maintenance testing.
' No-violations or deviations were identified.
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6.
Onsite Follow-up of Events at Operating Power Reactors (93702)
On June 18, 1990, an auxiliary operator discovered the motor of B Component Cooling Water Pump to be hotter than normal.
An investigation into the event revealed the chiller water outlet valve XVT-6446A-VU was closed rather than open, and the cross connect valve XVT-6446B-VU between pump B and C was open rather than closed.
The r.otor ran for approximately 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> without any cooling water and the motor stator reached a maximum temperature of 143 degrees C.
This temperature exceeded the alarm setpoint of 60 degrees C.
Engineering analysis evaluated the effects on the motor and concluded that the temperature did not exceed the maximum design temperature and no degradation of the insulation or other non-metallic parts had occurred.
The valvcs were apparently mispositioned on June 10, 1990, while perfo-ming System Operating Procedure (SOP - 118), Component Cooling Water, swr
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train-B to train-A.
The sign off sheets in the procedure were signcs verified by two auxiliary operators that valve XVT-6446B-VU was clo. :
when in fact it was open.
The outlet valve XVT-6446A-VU is not includeu in the attachment sheet for S0P-118, because the valve is normally open.
This valve position is verified on a monthly basis by STP-122.
It appears that the operators mismanipulated valve XVT-6446A-VU rather than XVT-6446B-VU and signed the lineup sheet on S0P-118 that valve XVT-6446B-VU was closed.
This mismanipulation of valves is a violation and it will be identified as violation 90-18-01, Failure to follow procedures.
This violation is similar to violation 90-06-01, identified in inspection report 90-06, Turbine driven emergency feedwater air supply valves mismanipulated.
in both cases, the valve verification process is
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In the TDEFW pump event, the "alves were very close together.
In this event the valves were separated by 15-20 feet, easily identifiable and located above each motor. The licensee is investigating the root cause of this event.
7.
Other Areas Inspection Report 89-22 addressed the Safety Evaluation which NRR issued on the use of the don-safety grade battery charger on the 125 VDC station battery banks.
The evaluation recommended that the licensee revise their administrative prucedures to include the three recommended limits for the use of the single cell charger.
The licensee revised Electrical Maintenance Procedure 115.004, Individual Cell Charging Procedure, to include all three requirements referenced in the Safety Evaluation.
The inspector verified the changes were made to the procedure and the recommendations were satisfied.
One regional inspecti,
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Mr.' Larry ' Cohen from the EP Branch, MRR and Ms. Ann Boland, EP Section, Region ll, visited the. site and corporate offices for review of plans to-relocate the E0F-to the corporate office of SCE&G.
Mr. Jack' Hayes, PM, visited the site for one week in conjuction with: the EOF review and held
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8.
- ExitInterview-(30703)
The inspection scope and findings were summarized on June 29, 1990, with those' persons indicated _ in paragraph _1.
The inspectors described the areas inspected and-discussed the inspection' findings.
The violation associated with mispositioning of component. cooling water valves was
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The visit by NRC-personnel on the projected move of-the E0F was also discussed.
No dissenting comments were received from the licensee. The licensee did not identify as proprietary any of'the materials provided to or reviewed-
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10.
Acronyms,and Initialisms EFW Emergency'Feedwater E0F
. Emergency Operations Facility
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'ESF-Engineered Safety Feature FW..
Feedwater LER-Licensee Event Reports MWR-Maintenance Work Request NRC Nuclear Regulatory Commission-NRR Office of Nuclear Reactor Regulation PMTS~
Preventive Maintenance Task Sheet
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Reactor _ Coolant System-RCSLK9 Reactor Coolant System Leak Rate
.RWP Radiation Work Permits
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t-SG Steam Generator.
SPR-Special Reports STP.
Surveillance Test Procedures TDEFW Turbine Driven Emergency Feedwater_ Pump TS Technical Specifications
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