IR 05000267/1986020

Insp Rept 50-267/86-20 on 860616-0815.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety Verification,Surveillances,Esf Maint,Security & Regional Peaking Factor

ML20212Q050
Person / Time
Site:	Fort Saint Vrain
Issue date:	08/28/1986
From:	Farrell R, Jaudon J, Michaud P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20212P660	List: IR 05000267/1986020 ML20212P658
References
50-267-86-20, NUDOCS 8609030389
Download: ML20212Q050 (5)

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f APPENDIX U.S. NUCLEAR REGULATORY COMMISSION l REGION IV NRC Inspection Report: 50-267/86-20 License: DPR-34 Docket: 50-267 Licensee: Public Service Company of Colorado (PSC)

Facility Name: Fort St. Vrain Nuclear Generating Station (FSV)

l Inspection At: Fort St Vrain Nuclear Generating Station, Platteville, Colorado Inspection Conducted: June 16 t ough August 15, 1986 t

Inspectors: ~ ' R. E. Rarrell, Senior Resident inspector (SRI) hdd Date l

Y ?' N P. MilhuY , Red tor 'specto / Date

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Approved:

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MM J. f. J4ud . Chief. Pryject Section A Date Flragt(r rojects Branch Y

Inspection Summary 11spection Conducted June 16 through August 15, 1986 (Report 50-267/86-20) .

Areas Inspected: Routine, unannounced inspection of operational safety verification, surveillances, en0ineered safety features, maintenance, security, and regional peaking facto Results: Within the six areas inspected, no violations or deviations were identifie .

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l DETAILS l Persons Contacted Principal Licensee Employees T. Borst, Support Services Manager / Radiation Protection Manager L. Brey, Manager Nuclear Licensing and Fuels

• R. Craun. Site Engineering Manager l M. Deniston, Shift Supervisor l T. Dice, Shift Supervisor i D. Evans, Superintendent Operations I

• M. Ferris, QA Operations Manager l *C, fuller Station Manager i *J. Gahm Manager Nuclear Production

• A. Greenwood, Supervisor, QA Auditing

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! J. llak, Shift Supervisor M. llolmes, Manager, Nuclear Service',

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• F. Novachek Technical / Administrative Services Manager 11. 0'llagan, Shif t Supervisor T. Prenger. QA Services Manager

• R. Schleiger, Supervisor, llealth Physics S. Shafer, Shif t Supervisor J. Sills, Supervisor Technical Services Engineering

• L. Singleton, Manager QA

• D. Warembourg, Manager Nuclear Engineering l S. Wilford, Superintendent of Training R. Williams, Vice President, Nuclear Operations ,

The SRI also contacted other licensee and contractor personnel during the inspectio * Denotes those attending the exit interview conducted August 15, 198 . Operational Safety Verification The SRI reviewed licensee activities to ascertain that the facility is being operated safely and in conformance with regulatory requirements and

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that the licensee's managernent control system is effectively discharging i its responsibilities for continued safe operatio The review was conducted by direct observation of activities, tours of the facility, interviews and discussions with licensee persennel, inde-pendent verifications of safety system status and limiting conditions for operations, and review of facility records.

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Logs and records reviewed included:

. Shif t supervisor logs

! . Reactor operator logs

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. Equipment operator logs

. Auxiliary operator logs

. Technical specification compliance logs

. Operations order book

. Operations deviations reports

. Clearance log

. Temporary configuration reports

. Station service requests (SSR)

During tours of accessible areas, particular attention was directed to the following:

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. . Monitoring instrumentation

. Radiation controls

. Housekeeping

. Fluid leaks

. Piping vibrations

. llanger/ seismic restraints ,

. Clearance tags

. Fire hazards

. Control room manning

. Annunciators No violations or deviations were identifle . Survol11.inces During the inspection period, the NRC inspectors observed the weekly surveillance tests of the emergency diesel generators and the annual discharge test of the station batteries. Additionally, work crews were observed performing visual inspections of prestressed concrete reactor vessel tendon No violations or deviations were identified in this inspection are .

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, * o-4- Engineered Safety Features During the inspection period, the inspectors verified the readiness to start capability of the emergency diesel generators and fire water pump The NRC inspectors verified the alignments of the station batteries and their full charge status. The NRC inspectors noted that the reserve shutdown system backup helium bottles had been removed during this period for maintenance, but this was acceptable since all control rods were full in and disable No violations or deviations were identified in this inspection are . Maintenance For this inspection period, the plant was in shutdown for an extended environmental qualification modification effort and turbine outage. Many maintenance items are being performed in conjunction with these efforts or in parallel with these effort During the inspection period, the inspectors observed the following maintenance activities:

. heavy load lifts on the turbine deck

. lifts of missile shields over the prestressed concrete reactor vessel

, core reflector block handling with the fuel handling machine

, drilling of core reflector blocks to take samples in the hot cell facility

. decontamination of the hot cell faci;ity

. maintenance of the reserve shutdown system

. rewiring of electrical junction boxes to meet the requirements of 10 CFR 50.49 No violations or deviations were identified in this inspection are . Security During this inspection period, the licensee continued work to upgrade the security systems. The NRC inspectors observed conduit placement, cable pulling, and concrete placemen The plant is still utilizing a substantial number of watchmen as compen-satory secu.-ity measures. The NRC inspectors found the watchmen to be in place and attentive. During construction efforts around the perimeter of L _ . - _ _ _ - _ _ _ _ _ _ _ _ - _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ - - _ _ - ._- _J

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-5-the plant, the inspectors observed the lead security officers evaluating and placing watchmen as compensatory measures as appropriate when perimeter barriers were degraded for purposes of constructio No violations or deviations were identified in this inspection are ' Region Peakina Factor The SRI reviewed the licensee's Procedure SR 5.1.7-X, Issue 4, " Region Peaking Factor Surveillance," and the records of this surveillance performed on June 21, 1984, and May 30, 198 .,

No violations or deviations were identified in this inspection are . ' Exit Inte view The SRI conducted an exit interview on August 15, 1986, attended by those indicated in paragraph 1. The SRI reviewed the scope and findings of the-inspection at this meetin ,

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