IR 05000267/1987001

Insp Rept 50-267/87-01 on 870202-06.No Violations or Deviations Identified.Major Areas Inspected:Fire Protection/Prevention Program & Implementation

ML20207R861
Person / Time
Site:	Fort Saint Vrain
Issue date:	02/27/1987
From:	Hunter D, Murphy M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20207R857	List: IR 05000267/1987001 ML20207R856
References
50-267-87-01, 50-267-87-1, NUDOCS 8703180220
Download: ML20207R861 (6)

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~ APPENDIX

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U.S. NUCLEAR REGULATORY ~COMISSION REGION IV,

NRC Inspection Report: '50-267/87-01 License:

DPR-34 Licensee:

Public Service Company of Colorado-(PSC)

P. 0.-Box 840-Denver, Colorado - 80201-0840.

Facility Name:

Fort St.-VEain Nuclear Generating-Station (FSV)

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l Inspection At:

Platteville, Colorado

'InspectionConducted:iFebruary'2-6,1987:

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' Inspector:

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i M. E. Murppy, Pn6jecFInspector, Project Dat'e Section/B, Reactor Projects Branch

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Approved:

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D. R. Hunter, Chief, Project Section B, Date Reactor Projects Branch

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Inspection Summary

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Inspection Conducted February 2-6, 1987 (Report 50-267/87-01)

l Areas Inspected:

Routine, unannounced inspection of fire protection / prevention program and implementation.

Results: Within the area inspected, no violations or deviations were identified.

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8703180220 870304 l.

PDR ADOCK 05000267 O

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DETAILS 1.

Persons Contacted

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• W. Dender, Jr., Nuclear Licensing Coordinator

• D. Edmiston, QA Training Engineer

• D. Evans, Superintendent, Operations

• M. Ferris, QA Operations Manager

• M. Holmes, Nuclear Licensing Manager

• T. McIntire, Supervisor, Nuclear Site Engineering

• F. Novachek, Technical / Administrative Services Manager

• G. Schmalz, Fire Protection Engineer

• A. Stithem, OIAG Coordinator J. Switzer, Training Instructor

• P. Tomlinson, Manager, QA F. Trujillo, Senior Designer

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The NRC inspector also contacted other licensee personnel including administrative, clerical, and operations personnel.

• Denotes those attending the exit interview.

2.

Status of Previously Identified Inspection Items (Closed) Violation 267/8412-10, Failure to Maintain Fire Barrier Penetration Sealed: The licensee has sealed the specific penetration.

Fire area boundaries and boundary ratings are being completely redefined as part of the overall Appendix R compliance review. These aspects will be evaluated during the scheduled Appendix R inspection. This item is

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closed.

(Closed) Deviation 267/8412-09, Failure to Meet Commitments in Res)onse To Branch Technical Position 9.5-1: The licensee has removed the )ulk combustible material from the reactor building and established, by

procedure revision, administrative controls for bulk combustibles. The

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hydraulic oil mist detectors had been installed and were operable. The additional fire detectors in various locations have been added. This work i-was accomplished under CN-846, approved May 16, 1985, and completed January 14, 1987. This item is closed.

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(Closed) Unresolved Item 267/8412-06: This item was pending the l

licensee's investigation and acquisition of documentation confirming that

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Overly Manufacturing Company was authorized to double label a fire area boundary door for both bullet proof and fire proof ratings. By letter

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dated August 14, 1984, from Underwriters Laboratories, Inc. to PSC, the

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licensee now holds adequate documentation that the Overly Manufacturing l

Company is properly listed with UL for both rating categories. This item l

'is closed.

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.(Closed) Unresolved Item 267/8412-07:.ThisLitem was pending resolution of:

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.the: questionable exposed metal structural members throughout the plant.

The specific. item of concern was the exposed metal I-beam cap on the

'3-hour fire rated wall separating level 5 into two fire areas in building 10.-

The licensee.has now. classified level 5 of building 10 as one fire area'and the I-beam was not structurally required in the' abutting

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walls.

The item is' closed.

(Closed) Unresolved Item 267/8412-08:

This item was pending the licensee's decision and action in assigning a specific individual to

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handle the overall. day-to-day management of'the fire protection / prevention program onsite.

The licensee has hired a full-time fire protection

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engineer.into their Nuclear Engineering Division. -This individual is well qualified and presently spends a significant amount of his time-onsite.

Future plans lare to assign an onsite individual the day-to-day management of-the program.

This itam is closed.

'(Closed) Open Item 267/8412-03:

This item was open pending installation 1

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.and satisfactory testing of a remote alarm / trouble indication in the control-room for areas of' building 10 that contain or are planned to contain' safety-related equipment..The licensee issued CN-846 to install the' indication.

This CN was completed January 14, 1987.

This item is

closed.

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(Closed) Open Item'267/8412-04:

This; item was open pending installation.

and successful,.' testing of battery room 1C air flow indication.

The licensee issued CN-1849'to install an' air' flow indication and remote alarm in the control ~ room.

This.CN-1849 physical-installation and testing has been completed. This item is closed.

(Closed) Open Item 267/8412-05: 'This item was open pending the 1icensee's

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action to establish a unit identification system for portable extinguishers.

The licensee' issued CN-1674 to' renumber plant fire

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extinguishers and hose stations.

This CN was completed May-20, 1985.

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-This item is clo' sed.

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Fire Protection / Prevention Program This inspection was to evaluate the overall adequacy of the licensee's program and to determine that the licensee was implementing the program in

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conformance with regulatory requirements and industry guides and i

standards, sThe NRC inspector ^ reviewed the following FSV procedures:

s Number Title Date

ADM-P-8 Fire Fighting and Prevention 03/26/86 SMAP-24 Fire Prevention Work Permit 01/02/86

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QAMP-P-8-1-Quality Assurance Monitoring Checklist ^

Fire Brigade Training and Fire Drill 09/06/85-PGEP-14 Fire Prevention / Protection Policy 02/01/82 50P 45-01 Fire Protection System 06/13/85 50P 45-02 Halon Fire Extinguishing Systems 04/30/85'

MAP-17 Requirements During Performance of Maintenance on FSV Fire Rated Doors 07/24/86 PM 45.9 Preventive Maintenance on Fire Water Deluge Valves 05/01/85 TPAM Situation Response Training Program -

Fire Fighting 01/29/86

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~ Discussion of Fire 08/14/84 FSP-1 Fire Fighting Organization and Responsibilities 04/01/86 FSP-2 General Instructions 10/27/83 FSP-3 Portable Fire Extinguisher Use 10/14/86 FSP-4 Hose Water Streams in Fire Fighting Near Live Electrical Apparatus, Inside the Plant 06/10/86 FSP-6 Halon System Operation 12/29/82 FSP-7 Carbon Dioxide Extinguishing Systems 12/29/82 FSP-8 Emergency Breathing Equipment 06/14/82 FSP-10 Flammable and Hazardous Compressed Gases 10/07/86 FSP-11 Fire Fighting Response Guidelines and Specific Area Preplans 01/07/87 FSP-12 Hazardous Material Marking 12/29/82 FSP-13 Hydraulic Oil Isolation Valve Locations and Guidelines 04/22/83 FSP-14 Additional Fire Fighting Equipment 10/18/83 FSP-15 Use of Portable Smoke Ejectors 01/07/87

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-5-This review verified that the licensee had technically adequate procedures to implement the fire protection program.

Procedural guidance was provided to control combustible material and reduce fire hazards.

Administrative procedures also provided for maintenance and surveillances on fire suppression, detection, and support equipment. Personnel training, qualifications,'and responsibilities were adequately provided.

Maintenance evolutions that significantly increase fire risk were properly controlled.

The NRC inspector toured accessible areas of the plant site for general area condition, work activities in progress, and visual condition of fire protection systems and equipment. Combustible materials, flannable and combustible liquid and gas usage were restricted or properly controlled in areas containing safety-related equipment and components.

Items checked included positions of selected valves, fire barrier condition, hose stations, hose houses, halon systems lineups, fire lockers; and fire extinguishers for type, location, and condition.

During this tour, the NRC inspector noted two fire doors, between the reactor building and building 10, that were not closing completely due to the air pressure differential. The licensee representative accompanying the NRC inspector took imediate action to have the door closing mechanisms adjusted to provide positive closure for the doors.

There was no welding, cutting, or use of open flame ignition sources found in the areas toured. There were no construction activities in progress in the toured areas. There was some maintenance work noted. General housekeeping conditions _were found to be excellent.

Fire protection systems and equipment installed for protection of safety-related areas were found to be functional and tested in accordance with the requirements specified in the Technical Specifications.

Fire brigade equipment, including emergency breathing apparatus, was found to be properly stored and maintaired.

The NRC inspector also reviewed fire brigade training and drill records.

The records were in order and confinned that training and drills were being conducted at the specified intervals.

The last annual in-house QA audit in the area of fire protection, NFSCH-86-1 dated August 14, 1986, was reviewed by the NRC inspector. The audit was comprehensive and indepth. System / equipment alterations, tests, surveillances, maintenance, and records were addressed. Discrepancies identified were formally presented to the affected organization. Responses were tracked to closeout and actions taken were reviewed for adequacy.

These discrepancies were issued as Correction Action Requests (CAR).

During this audit review, the NRC inspector reviewed CAR-85-091 and CAR-85-092. CAR-85-091 dealt with the fire rating of the east wall of the

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auxiliary boiler room and had been closed by QA with no apparent problems.

CAR-85-092 dealt with the compliance of the suppression systems for the "J" and "G" walls to the installation requirements of NFPA-13. This CAR had also been closed by QA and had an extensive history of correspondence between the licensee's engineering group, the licensee's insurer, Professional Loss Control, Inc., and the licensee's fire protection

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consultant, TENERA Corporation. The documentation package did not appear l

to support the final closure of this CAR because it did not address the concerns raised in the last Professional Loss Control, Inc., memo of

- April 3,1986. This issue will be referred to NRR for review. Pending e

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NRR disposition and subsequent review this matter will be considered an unresolveditem(267/8701-01).

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There were.no violations or deviations identified in this area of ~ the i

inspection.

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Unresolved Items An unresolved item is a matter about which more infomation is required to

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detemine whether it is acceptable, a violation, or a deviation. One unresolved item is discussed in this report in paragraph 3.

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5.

Exit Interview

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i An exit interview was conducted on February 6,1987, with those personnel

denoted in paragraph 1 of this report. At this exit interview, the NRC l

inspector summarized the scope and findings of the inspection.

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