IR 05000267/1990017

Insp Rept 50-267/90-17 on 901001-1109.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety, Monthly Surveillance & Maint Observation

ML20058K028
Person / Time
Site:	Fort Saint Vrain
Issue date:	11/29/1990
From:	Constable L, Garrison D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20058K025	List: IR 05000267/1990017 ML20058K023
References
50-267-90-17, NUDOCS 9012060268
Download: ML20058K028 (6)

Text

_ ._ _ . - ..

<. 1

, .

,1 i

'

.

...

\

'

' [ '

APPENDIX l

b V.S. NUCLEAR REGULATORY C0 MIS $10N

REGION IV

NRC Inspection Report: 50-267/90-17 Operating License: DPR-34 Docket: 50-267 Licensee: Public Service Company of Colorado (PSC)

P.O. Box 840 -

Denver, Colorado 80201-0840 l Facility Name: Fort St. Vrain Nuclear Generating Station (FSV)

l Inspection At: FSV, Platteville, Colorado inspection Conducted: October 1 through November 9,1990 Inspector: i / i'de /40

/D "

i . L.-Garrison, Reactor Inspector, Division Date of Reactor Safety

-

,

d 's Approved:- / 6 ~~~ ~' ///2 M/v (L. Cbnstable. Chief, Technical Support Section Date '

Division of Reactor Projects Inspection Summary .

-

Inspection Conducted October 1 through November 9.1990_ (Report 50-267/90-17) -

Areas Inspected: Routine, announced inspection of operational safety verification, monthly surveillance observation, and monthly maintenance observatio .

Results: Within the areas inspected, no violations or deviations were identified; however, one inspector followup item was identified. .The licensee; I performed maintenance activities for plant systems and components in an '

i adequate manner and performed required surveillances in accordance with the-Technical Specifications. Plant operations were conducted in a safe manner j and in .conformance with requirements applicable for the current status of the '

" 'j plant., The licensee is maintaining a reduced, but qualified and experienced,  !

'

staff of craftsmen, engineers', operators, and management staff sufficient to maintain compliance with Technical Specifications and other regulatory .

L = requirement l h

1'

L u l 901 Toe 0;6e AD0cm aoi;6pg OSog .j

[_]DR P q

,

\

.

--a s _ e--- , ,

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

. .

.

.

.

'

DETAILS PERSONS CONTACTED PSC

• C, Crawford, Vice President, Nuclear Operations

• C. Fuller, Manager, Nuclear Production

• D. Warenbourg, Manager, Nuclear Engineering

• H. Brey, Manager Nuclear Licensing and Resources

• M. Holmes, Manager, Nuclear Licensing

• F. Borst, Manager Nuclear Training and Support

• P. Tomlinson, Manager, Quality Assurance

• J. Gramling, Supervisor, Nuclear Licensing, Operations

• M. Deniston, Superintendent of Operations NRC

• J. Baird Senior Resident Inspector The inspector also contacted other licensee and contractor personnel during the inspectio * Denotes t. hose in attendance during the exit interview conducted November 8, 199 . PLANT STATUS The plant was permanently shut down August 18, 1989. One third of the fuel has been removed from the core and placed in spent fuel storage wells. The motor control center breakers for the control rod drives are o>en, racked out, and n clearance tagsed. The licensee awaits pennission from tle Department of Energy (DOE) to initiate shipment of irradiated fuel to the DOE Idaho National

'

Laboratory facility. Irradiated fuel was previously shipped to DOE Idaho following each plant refuelin An NRC confirmatory order prohibiting operation at any power level was issued May 1, 1990. On May 16, 1990, the Federal Register contdined an announcement ,

of intent by the NRC to amend the fac111ty license to preclude operation at any i power level.

l The licensee has submitted a construction application for an independent spent  !

'

fuel storage facility (ISFSI) as a contingency in the event shipnent to DOE Idaho is significantly delayeo. This application is under revie The plant is currently in a defueling mode with the vessel partially defueled and is awaiting approval of a possession-only license (POL) application in order to proceed with other scheduled work. Although the licensee has established schedules of activities, they are in a hold status until a detenuination is made regarding the shipment of irradiated fuel from the site, j l l l l

\. - . .-. . - . , . .

_ _ _ _ _ . _ _ _ -

. .

.

.

.

,

Maintenance and surveillance activities are continuing and nonneeded equipment :

is being placed in a layup status. Preconstruction work is continuing on the ISFS . MONTHLY MAINTENANCE OBSERVATION (62703)

Licensee maintenance activities for plant systems and components were observed in order to verify that the work was conducted in accordance with approved procedures and standard The following monthly maintenance activities were observed by the inspector in order to assure that the licensee maintenance program for plant systems an4 components was being implemented in accordance with established procedures and specification .1 Maintenance on Instrument Air Compressor C82015 - Procedure HP-7055(A)

Issue 2. June 1,1989 "Gardner-Denver Instrument Air Compressors" Annual overhaul, Station service Request (55R) 90b02655 The inspector witnessed several steps of work in the procedure, which included five inspections over a period of 5 days. This machine is a single cylinder horizontal dry compressor with a 12-inch bore and 9-inch stroke. The maintenance work included complete disassembly, reworking, installing new components, and reassembling the entire compressor. The mechanic was well versed in the procedural aspects and the mechanical requirements and discussed the overhaul with the inspector. Two weeks after the last inspection, the inspector noted that the machine nad been returned to service and was performing satisfactoril .2 Replacement of a Throw-Out Bearing on Diesel Engine IC - Procedure NP-7090, I Issue 4, July rd, Ivuu, "stenaby Diesel Generator" During c monthly surveillance it was found that the IC and ID diesel engines were not carrying an equal load in powering the Emergency Generator IB. The I load on the generator was limited to 700 kW. An evaluation by maintenance found that the clutch was not fully engaging on the 10 diesel engine. The clutch mechanisms on these units are hydraulically operated and similar to automotive types. They consist of a "y" or yoke extending through and pivoting on the bell housing of the engine. The yoke engages the throw-out bearing which rides on a splined shaft and engages the fork on the pressure plate which acts on the clutch dis l The equipment problem was that the throw-out bearing, which has a collar and grease hose attached, wore down and the collar and hose started turning, preventing complete pressure plate engagement; thus, the clutch was not fully l engaged. The mechanics replaced the throw-out bearing which corrected the problem. The inspector verified that the equipnent was tagged out in the control room and motor control centers and that the replacement was performed in accordance with the procedur l

- - -

- -- -- _ _ _ - -- -- -.-. ... . -

. l

-

\

-

I

i l

3.3 Fuel Block Inspection and Poison loading - Procedure MPF 1230, Issue 4, October 3,1993 "Defueling Block Inspection and Poison Loading,"

55R 89505323 The process involves 1350 blocks of gra)htte that are machined to the exact dimensions of the fuel blocks used in tie reactor. The purpose of the blocks will be to replace the irradiated fuel blocks when they are removed to the spent fuel facility; these blocks will keep the core f rom shifting. The blocks are drilled with 102 air holes which penetrate approximately 33 inches into each block. Twelve of the holes are used to insert boron carbide pellets which will control criticality in the reactor as the highly irradiated fuel is remove When the inspector observed the process,1221 blocks had been finished and approximately 190 blocks were left to be completed. All dinensional checks, placement of the poison, sealing of the holes, and recordkee)ing by a quality inspector were observed and found to be in accordance with tie governing procedure. The defueling blocks are kept on the turbine deck in 55-gallon )

insulated drum .4 M_aintenance Training on Cask Trailers - Procedure MPF 7004, Issue 2, March 29,1990, " Fuel Shipping Cask Semi-Trailer Level 1 Inspection,"

Monthly The inspector accompanied a training instructor as he 3rovided procedura11 red training to two craftsmen on the monthly inspections t1at are to be performed on the semi-trailers that specifically haul only one type of fuel cask. The trailers are triple axle Fruehauf Model BM-NF2-40Ns; the specific trailer was Serial No. 1H5PO4035L M022101. The instructor went through the procedure step-by-step, pointing out the items he was explaining and the reasons they were critical to the inspection process. The instructor had in his accompaniment a cut-away model of the air brake cylinders, a lighting functionel test device for remotely actuating the lights and turn indicators, and a brake test instrument for brake function with the use of remote ai .5 Liquid Waste Demineralizer - Procedure MP 2247, Issue 1, May 11,1988,

" Liquid Waste Dem1neralizers," 55R 90502797 - RWP 11439 The inspector witnessed the removal of Liquid Waste Demineralizer 1B by the mechanical maintenance department. The demineralizer cartridge was plugged which necessitated the replacement. The mechanics removed and replaced the entire unit as the resins are cleaned elsewhere in the plant. The work was monitored by a health physics technician in accordance with Radiation Work Permit (RWP)11439. The work procedure, RWP, and SSR provided adequate instructions and recording of the work effor .6 Fabrication of Penetration Fixture - Engineering Evaluation (EE) 21-00132 Revision A. July 26.1990 " Design Analysis, and Assembly of Fixtures for Closure of Helium Circulator Penetrations," 55R 90502573 When the "B" helium circulator was removed from the reactor, a large valve was placed on the external bottom side to provide closure of the vessel. In order to remove the "A" circulator, the valve will have to be removed from the "B"

_ _ _ _ ___ .__- _ _ _ - _ _ -

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

.

. . 1

.

.

i unit as the licensee has only one valve of this typ This requires the I fabrication of a fixture that is rearly identical to the removed ,

"B" circulator. The inspector reviewed the engineering design and set up of  !

the components which will be welded to form an assembly which will be inserted into the "B" circulator position to seal the penetration. The inspector i discussed the process with the craftsmen and design engineer and was not .

satisfied that the evaluation and procedures were adequate; however, the I fabrication of the unit was halted due to a fabrication error and a hold was placed on the work by quelity assurance who objected to the work being perfonned i under an EE while classed as safety related. The inspector will review this i'

process during a later inspection. Inspector Followup Item 267/9017-0 . HONTHLY SURVEILLANCE OBSERVATIONS (61726)

The nonthly surveillances for plant systems was inspected in order to observe the licensee activities of safety-related systems and detennine if these systems were being maintained in accordance with the Technical Specification . Surveillance and Operation of Plant Recorders - Procedure SR-0P-29- '

Tssue 13. August 10.1990 " Plant Recorders" The satisfactory implementation of this procedure will assure that the plant recorders outside of the control room are properly operating and recordin Thirty-one recorders are checked in the service water system, shallow wells, meteorology tower, river water systems, demineralizer rooms, and turbine building. This surveillance is relatively simple and only requires the proper inking, timing, and operating mode. The surveillances are performed dail The inspector reviewed the records for the week of October 29 through November 2,1990, and found that the surveillances were performed as require .2 Emergency Lighting - Procedure SR-FP-20b-4, Issue 3. September 28, 1990

" Emergency Lighting Functional Test" - Electrical Maintenance - Quarterly

>

The licensee utilizes both ac.and dc emergency lighting in systems throughout the plant. Some of.the ac functional tests require the deenergization of breakers that supply large areas of the plant and some are single room,  ;

one light units. Dc systems are also arrayed in.like systems and are powered by individual battery banks and the auxiliary cooling method (ACM) diesel L generator batteries. The inspector accompanied the electrician performing the functional testin water pump room (g N92152),

fixture and witnessed themotor-driven the electric tests in thefire dieselpumpengine-driven room fire (Fixture N92151), and the circulating water makeup pump house.(Fixture N92148).

The only problem noted during the inspection was that six lights on the snubber deck were not working. The licensee generated a SSR to expedite the repair of-these units. A quality assurance surveillance inspector accompanied the electrician on a random basi __ __ . _ _ _ _

. .

.

.

-

4.3 Emergency Diesel Generators - Procedure SR-OP-57-W, Issue 1, February 6, Ivvu, "o11 cleanup of tmergency Diesel Generators" - Operations - Keekly The emergency diesel engines that drive the emergency generator require the  ;

cleanup of oil on the sets due to leaking gaskets, seals, and lines. The ,

leakage is normal and is considered minimal. During the cleanup of Diesel 10, i the inspector found a valve handle in the engine skid basin; it was determined that the handle had vibrated loose from an air starting line bypass which was mounted up-side-down. The operator found the securing nut and replaced the handle. A later inspection revealed that the operator had done an outstanding job in cleaning both engines in the No. I set. The engines are Caterpillar .

Turbocharged Vee 12s back-to-back with the generator in the center of both j units. The operator reported the up-side down valve and other like valves on  !

the engines as problem area j OPERATIONAL SAFETY VERIFICATION (71707) l l

'

The objectives of the inspections were to assure that the licensee was operating the plant in a safe manner in conformance with procedures. Technical Specifications, and regulatory requirements and management controls and that activities of the licensee radiological protection programs are in conformance with plant procedures and regulatory requirements. Even though the plant is in Mode 6, surveillance requirements are mandator The inspector conducted daily tours in all areas of the plant and reviewed documentation of equipment problems, plant schedules of ongoing work, and plant logs. The plant tours and attendance at scheduling meetings kept the inspector cognizant of the ongoing work effor The ._. vetor brought to the licensee's attention sone areas of minor concern identified during plant tours and observation of surveillance Areas inspected that were found to be satisfactory include fabrication of storage casks, yard and security fencing, general meintenance, control room demeanor.and operation, and cleanliness of the facility and storag No violations or deviations were identified in the review of this program area, t EXIT MEETING (30703)

An exit meeting was conducted with licensee representatives identified in paragraph 1 on November 8, 1990. During this interview, the inspector reviewed the scope and findings of the report. The licensee did not identify as proprietary any information provided to, or reviewed by, the inspecto ._- -