IR 05000267/1986029

Insp Rept 50-267/86-29 on 861001-1115.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety Verification,Licensee Action on LERs & on Previously Identified Insp Items & Followup of Allegation 4-86-A-081

ML20215D820
Person / Time
Site:	Fort Saint Vrain
Issue date:	12/01/1986
From:	Farrell R, Jaudon J, Michaud P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20215D811	List: IR 05000267/1986029 ML20215D808
References
50-267-86-29, NUDOCS 8612170051
Download: ML20215D820 (8)

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APPENDIX e

U. S. NUCLEAR REGULATORY COMMISSION REGION'1V

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NRC Inspection Report: 50-267/86-29 License: DPR-34 Docket: 50-267<

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Licensee: Public Service Company of Colorado (PSC)

Facility Name: Fort St. Vrain Nuclear Generating Station Inspection At: Fort St. Vrain (FSV) Nuclear Generating Station, Platteville, Colorado and PSC Offices, Denver, Colorado Inspection Conducted: October 1 through November 15, 1986

- Inspectors: Jdda// //~@~8%

R. E. FarVell, Seni6r Resident Inspector (SRI) Date

//"24S P. W. Michaud, Hesident Inspector (RI) Date

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Approved: w /2 8 f. P( J on, Chief," Project Section A Dath L Reac Projects Branch ADO K 7 hbk G

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Inspection Susunary

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Inspection ' Conducted October 1 through Nbvember 15,1986.(Report 50-267/86-29)

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Areas-Inspected: Routine, unannounced inspection'of operational safety verification, licensee action on licensing event reports, licensee action on

- previousli;. identified. inspection findings,' followup of Allegation 4-86-A-081,

- maintenance,'; engineered safety feature's, and securit '

Resul'ts: ~ Within the seven areas inspected, no violations or deviations were

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DETAILS- Persons Contacted Principal Licensee Employees D.-Alps,' Security Supervisor

• T. Borst, Support Services Manager / Radiation Protection Manager D. Brown, I&C Supervisor :

R. Burchfield, Superintendent Nuclear Betterment J. Capone, Licensing Engineer R. Craun, Site Engineering Manager M. Deniston, Shift Supervisor J. Eggebroten, Superintendent Technical Services Engineering D. Evans, Superintendent Operations M. Ferris, QA Operations Manager

• C. Fuller, Station Manager

• J. Gramling, Supervisor Nuclear Licensing

' A. Greenwood, ~ Supervisor Quality Assurance Auditing S. Hofstetter, Nuclear Licensing Engineer

• J. Gahm, Manager Nuclear Production

• J. Jackson, Supervisor QA/QC

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-*0. Lee III, QA Auditor- .

• T. McIntire, Supervisor Nuclear Site Engineering F. Novachek, Technical / Administrative Services Manager T. Prenger, QA Services Manager-

• P. Tomlinson, Manager- QA D. Warembourg,- Manager Nuclear Engineering

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R. Walker, C. E. O. , Chairman of the Board R. Williams, Vice President Nuclear The NRC inspectors also contacted other licensee and contractor personnel during the' inspectio * Denotes those attending the exit interview conducted November 12, 198 . Operational Safety Verification The NRC inspectors reviewed licensee activities to ascertain that the facility is being operated safely and in conformance with regulatory requirements and that the licensee's management control system is effectively discharging its responsibilities for continued safe operatio The review was conducted by direct observation of activities, tours of the facility, interviews and discussions with licensee personnel, independent verifications of safety system status and limiting conditions for operation, and review of facility record ,

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Logs and records reviewed included: 4

. Shift supervisor logs '_

. Reactor operator logs 2

. Equipment operator logs ,

. Auxiliary operator logs  ?

. Technical specification compliance logs 2-

. Operations order book e

. Operations deviations reports c Clearance log

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. Temporary configuration reports  %

. Station service requests (SSR) 5 During tours of accessible areas, particular attention was directed to the

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. Monitoring instrumentation

. Radiation controls !_

. Housekeeping {

. Fluid leaks -ir

. Piping vibrations O

. Hanger / seismic restraints 2

. Clearance tags a

. Fire hazards -"'_=-

. Control room manning y

. Annunciators _T a

During the inspection period, the licensee experienced several spurious 4 scrams actuations due to high rate of change indications on wide range  ;

neutron flux channels 3 and 5. These are documented via notification to d the NRC on the ENS line and are being reported in licensee event report The inspectors are following licensee actions to troubleshoot and to

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prevent recurrence of these spurious actuations. The reactor remained  !

subcritical throughout the inspection period with all control rods in and =

disabled, thus there were no adverse consequences of these actuation y The licensee indicated that it is intended that the cause of these y actuations be found and corrected prior to restart of the plan a_

During the inspection period, the inspectors observed continuing  :

improvement in control room demeanor. The impact of the recent control =-.

room modifications including better sound absorption, lighting, and decor &

have had a noticeable impact on licensed operator morale. The addition of y barriers to limit access to the control panels has reduced congestion in -

the licensed operators work area and contributed to a more business like e atmosphere in the control roo Shift turnovers observed during the inspection period demonstrated a $

continuing improvement in shift to shift communication and operator @

attention to detai .

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The plant continued in a major outage for equipment environmental qualification, turbine overhaul, and miscellaneous maintenance activitie The cleanliness and general housekeeping in the plant have been maintained

at a high level for the amount of activity taking plac ,

No violations or deviations were identified in this inspection area.

' Licensee Action on Previous Inspection Findings  :

! (Closed) Violation (267/8517-01): Failure to Report Helium Circulator

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Trip in Accordance with 10 CFR 50.73.

Single helium circulator trips have been determined not to be reportabl This violation was subsequently withdrawn. The violation is closed in this report for record purposes.

! Licensee Action on Licensee Event Reports (LERs) -

Helium circulator trips and rod withdrawal prohibits previously reported as LERs have been determined not reportable. The following LERs do not -

address reportable events and are considered closed:

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(CLOSED) LER 85-030: Circulator Trip f (CLOSED) LER 85-031: Circulator Trip  ;

(CLOSED) LER 86-001: Circulator Trip i (CLOSED LER 86-002: Circulator Trip (CLOSED LER 86-003: Circulator Trip (CLOSED LER 86-005: Circulator Trip (CLOSED) LER 86-007: Circulator Trip (CLOSED) LER 86-004: Rod Withdrawal Prohibit (CLOSED) LER 86-012: Rod Withdrawal Prohibit '

(CLOSED) LER 86-014: Rod Withdrawal Prohibit (CLOSED) LER 86-015: Rod Withdrawal Prohibit No violations or deviations were identified in this inspection are m Followup of Allegation 4-86-A-081

Allegation 4-86-A-081: Unqualified Instrumentation & Control (I&C) -

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Technicians

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The NRC received an allegation regarding the certification of I&C i technicians at Fort St. Vrain. The concern, as initially stated, was that l technicians performing environmental qualification work were not qualified to do the work in that they did not meet " standards".

The NRC SRI interviewed the individual expressing the concerns. The individual's concern was the certification and qualification of permanent

licensee personnel functioning as I&C technician m I

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The SRI reviewed the qualifications of all permanent I&C technicians employed at Fort St. Vrain. These qualifications were compared to licensee consnitment The Fort St. Vrain Quality Assurance Program (FSAR Appendix B) commits to meeting the requirements of ANSI N18.1-1971. " Selection and Training of Nuclear Power Plant Personnel."

Paragraph 4.5.2 of ANSI N18.1-1971 requires that technicians have two years working experience and one year of related trainin The NRC SRI reviewed the resumes on file with the licensee for all 12 I&C technicians and for the two maintenance workers on loan to the results department from maintenance. Three individuals were interviewed by the NRC SR The individuals were all qualified for their positions according to the requirements of ANSI N18.1-197 The allegation was not substantiate No violations or deviations were identified in this inspection are . Maintenance-The NRC inspectors continued to monitor electrical equipment qualification activities. The inspectors witnessed installation of RAYCHEM splices and discussed various activities with craft and QC personnel. No discrepancies were note Maintenance activities continued on motor operated valves identified in response to IE Bulletin 85-03. Five SMB4T and three SMB3 limitorque operators were completely disassembled for inspection and replacement of lubricant. The NRC RI observed various portions of the disassembly of several of these valves. Inspection of the components indicated cracks were present on the worm gear of most of these larger operators. The worm

. gears were rejected after a magnetic particle examination was performe New parts have been ordered and the RI will continue to monitor work on these valve The RI witnessed the reinstallation of a prestressed concrete reactor vessel (PCRV) rupture disc which had been removed and tested in accordance with surveillance requirement SR 5.2.1. The working copy of Surveillance Procedure SR 5.2.la-X/5.2.lci-X, Issue 12, "PCRV Rupture Disc and Safety Valve Test," was reviewed to ensure compliance and coordination between the work activities and the steps of the procedur The NRC inspectors continued to monitor asbestos removal activities within the plant as well as other maintenance items. Hydraulic system Loop 2 modifications are currently complete with the exception of the relocation of hydraulic pump motor rectifiers for environmental qualification

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pu rposes. The environmentally qualified motors in the Loop 2 hydraulic system have been installed and the loop is in recirculation for cleanup prior to being restored to service. The hydraulic system Loop 1 environmentally qualified motors are in the process of being installe The inspectors also observed cable pulling, terminations, and junction box sealing during the inspection period. These were all environmental qualification activities. Pipe hanger additions and relocations were observed as well as valve seat lapping and prestressed concrete reactor vessel cooling water heat exchanger rebuilt activit No violations or deviations were identified in this inspection are . Engineered Safety Features The RI performed a walkdown of the PCRV overpressure protection system to verify its status and operability. The inspector reviewed Section 4 of the FSAR, Technical Specifications 3.2, 3.3, 4.2.7, and 5.2.1, and applicable drawings to become familiar with the system and requirement All portions of the system were physically inspected, including the internals of the PCRV safety valve tank. The as-found configuration, including valve positions and locking devices, was compared with system drawings and P&I diagram to determine agreemen Surveillance activities (rupture disc testing) caused several valves to be out? of their normal positions, but these valves were positioned correctly in accordance with the tagout in effect. With the exception of these valves, the inspector found no disagreement between the actual configuration and the drawing The overall condition of the system was good, and no discrepancies were foun 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 cable pulling, concrete placement, installation of towers for closed circuit television, installation of television cameras, and installation of microwave dntenna No violations or deviations were identified in this inspection are . Management and Exit Meetings During the inspection period, the NRC inspectors conducted a monthly meeting with licensee executive management to review progress on activities to correct SALP report identified weaknesses. Performance enhancement program activities were reviewed as well. The NRC inspectors met periodically with the plant manager and the site engineering manager to review progress towards completion of the environmental qualification

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A and other outage activities. Several meetings were held with the manager

.- of quality assurance to monitor changes in the corrective action request program and audit program An exit interview was conducted November 12, 1986, attended by those

-. indicated in paragraph 1. At this time the inspectors reviewed the scope and findings of the inspectio h