IR 05000324/1987025
| ML20237K632 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 08/20/1987 |
| From: | Conlon T, Harris J, Madden P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20237K594 | List: |
| References | |
| 50-324-87-25, 50-325-87-25, NUDOCS 8708270236 | |
| Download: ML20237K632 (18) | |
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A RfC UNITED STATES
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b NUCLEAR REGULATORY COMMISSION
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E REGION 11
'o 101 MARIETTA ST., N.W., SUITE 3100
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ATLANTA, GEORGIA 30303
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Report Nos.: 50-325/87-25 and 50-324/87-25 Licensee:
Carolina Power and Light Company P. O. Box 1551-Raleigh, NC 27602 Docket Nos.:
50-325 and 50-324 License Nos.:
DPR-71 and DPR-62 Facility Name:
Brunswick 1 and 2 Inspection Conducted:
July 27-31, 1987 Inspectors:N
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f #fz-
- b f-7o~97 d
P. M. Madden
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Date Signed 0/ )ctM$
f -/ 7 - F 7 A
J. R. flafrri s Date Signed
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Accompanying. Personnel:
J. Zeiler, NRC RII
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Technical Support Staff
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Approved
- .. E..Conlon, Section Chief Date Signed Engineering Branch Division of Reactor Safety SUMMARY Scope:
This routine, unannounced inspection was conducted in the areas of Fire Protection / Prevention, Follow-up on Previously Identified Inspection Items and Employee Concerns.
Resul ts':
No violations or deviations were identified.
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I B708270236 870824 PDR ADOCK 05000324
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F REPORT DETAILS p
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Persons Contacted
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Licensee Employees
- S. D.' Anderson, Project Engineer
- W. Biggs, Construction Engineer
- E A. Bishop, Manager Operations
- C, F. Blackmon, Radwaste/ Fire Protection Supervisor
.*L. R. Bryant, Document Control Specialist l
- S. Calls, Regulatory Compliance
- C. R. Dietz, General Manager
- E. R. Eckstein, Manager Technical Support R. E. Helme, Director On-Site Nuclear Safety
- K. E. Enzor, Director Regulatory Compliance
- D. J. Foti, Fire Protection-System Engineer
- R. 'J. Groover, Project Construction Manager
- R. S. Hill, Project Specialist-Construction
- L. E.- Jones -Director-QA/QC
- B. Knight, Construction Engineer
- T. Mull, Fire Protection Specialist-
- J. O'Sullivan, Manager Maintenance
- F. J. Reedy, Specialist-0perations
- T. L. Sarnes, Fire Protection Specialist-Training
- M. C. Shealy, Project Specialist-Training
- K. R. Waddell, Senior Specialist-Training NRC Resident Inspectors
- W. H. Ruland
- Attended exit interview i
2.
Exit Interview The inspection scope and findings were summarized on July 17, 1987, with those persons indicated in paragraph 1 above.
The inspectors described the areas inspected and discussed in detail the inspection findings.
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dissenting comments were received from the licensee.
The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspectors during this inspect' _ - _ _ _ _ _ _
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3.
Licensee Action on Previous Enforcement Matters a.
(Closed) Unresolved Item (324, 325/81-23-05), Fire / Flame Barrier Requirements for Service Water Pumps.
The NRC office of Nuclear Reactor Regulation (NRR) by letter dated December 30, 1986, granted the licensee an exemption to the Appendix R Section III.G.
fire I
barrier separation requirements for the service water building.
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Therefore, based on the NRR's acceptance of the licensee's service water exemption request, the installation of the flame barriers between the conventional and the nuclear water pumps would not greatly enhance the fire safety or reduce the potential for fire damage to safe shutdown systems room. This item is closed, b.
(Closed) Violation Item (324, 325/92-44-01), Having Non-Functional fire barrier penetrations without establishing fire watches.
Currently, the licensee is implementing a fire barrier seal improvement program which is currently scheduled to be completed by the end of 1W8. This improvement program along with the appropriate interim compensation measures (fire watches) was approved by the NRR
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I Safety Evaluation Report (SER) dated May 29, 1987. Therefore, based on the licensee's commitments to improve the plant fire barrier seals program. This item is closed.
c.
(Closed) Violation Item (325/83-11-01), Technical Specification 3.7.7.2 Limiting Condition for Operations (LCO) exceeded. As a result of a 1983 NRC inspection several fire protection programmatic problems were identified.NRC inspection report 83-11 identified that the y
licensee failed to adhere to the plant fire protection Technical J
Specifications LCO, failed to properly implement fire protection surveillance procedures, failed to make a prompt report of certain fire protection system deficiencies to the NRC and failed to make the required special reports to the NRC on these fire protection deficiencies.
In response to these fi re protection program weaknesses the licensee implemented a fire protection improvement
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program which improved the licensee's site fire protection organiza-l tion, revaluated the adequacy of the fire protection program administrative controls and surveillance procedures, improved the fire brigade training program, and implemented a fire protection retraining program for the plant fire brigade and operations personnel.
The licensee fire protection improvement program was fully implemented in 1985 and was inspected during this inspection and NRC routine fire protection program inspection number 325/86-30, and 324/86-31. Based on the results of these inspections, no program weaknesses or violations have been identified in the fire protection program inspection 325/86-30 and 324/86-31.
Based on the results of these inspections, no program weaknesses or violations have been identified in the fire protection area.
Therefore, this item is closed.
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(Closed) Violation Item (325/83-11-02, 324/83-11-01), Technical Specification 3.7.8.2 limiting condition for operations exceeded.
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See item C above of closeout.
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(Closed) Violation Item (325/83-11-03, 324/83-11-02), failure to implement fire protection surveillance procedures.
See item C above for closecut.
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(Closed) Violation Item (325/83-11-04), Failure to make a timely i
prompt report of fire protection deficiencies. See item C above for closeout.
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(Closed) Violation Item (325/83-11-05), Failure to make a special report of fire protection deficiencies.
See item C above for closecut.
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Unresolved Items
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Unresolved items were not identified during this inspection.
5.
Fire Protection / Prevention Program (64704)
a.
Fire Prevention / Administrative Control Procedures j
The inspectors reviewed the following Fire Prevention / Administrative Procedures:
Procedure No.
Ti tle FPP-05, Revision 2 Fire watch qualifications, duties and responsibilities FPP-013, Revision 2 Weekly fire inspection and plant housekeeping FPP-014, Revision 2 Control of combustibles transient fire loads, and ignition sources FPP-017, Revision 1 Control of cutting, welding and grinding EFP-03, Revision 0 Engineering fire procedure, fire hazards analysis EFP-04, Revision 0 Engineering fire procedure, fire hazards evaluation PLP-01, Revision 0 Fire protection program document
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Based on this review, it appears that the above procedures meet the NRC guidelines of the document entitled " Nuclear Plant Fire Protection Functional Responsibilities, Administrative Controls, and Quality Assurance" dated June 1977.
b.
Fire Protection Surveillance Procedures The inspectors reviewed the following Fire Protection System Surviellance Procedures:
Procedures No.
Title PT-35.1, Revision 31 Fire pump test - weekly PT-34.1.1.0, Revision 3 Diesel driven fire pump test -
weekly PT-34.2.1, Revision 2 Electric driven fire pump functional test - monthly PT-34.5.5, Revision 3 Diesel and electric fire pump functional test - annual PT-34.7.1.0, Revision 2 Fire suppression water system flow test - three years PT-34.6.4.1, Revision 1 Sprinkler and spray system visual inspection, reactor building Unit 1 - 18 months PT -34.5.1.3, Revision 2 Unit I reactor building fire protection valve cycle and standby gas treatment deluge system test - annual PT-34.5.1.5, Revision 2 Diesel generator building fire protection valve cycle test -
annual PT-34.5.1.6, Revision 3 Service water building, radwaste building and main water treatment building sprinkler and valve cycle test - annual PT-34.2.3.1, Revision 2 Hose station inspection reactor building Unit 1 - monthly PT-34.5.2.1, Revision 1 Hose station, hose and gasket removal and inspection reactor building Unit 1 - annual
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PT-34.7.2.1, Revision 0
. Hose station flow and. hose
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replacement reactor. building-l Unit 1 - three years PT-35.11.2, Revision 3 Hos'e rack surviellance'- 18 months-PT-35.11.3, Revision.4-Hose station operability and hose hydrostatic test - three years PT-35.16.1, Revision 5 Fire barrier penetration. seals reactor building-18 months PT-35.16.3, Revision 3 Fire barrier penetration seals service water intake structure -
18 months PT-35.16.4, Revision 7-Fire barrier penetration seal control building - 18 months PT-35.16.6, Revision 3 Fire barrier penetration seals.
control room panels and cabinets-
- 18 months PT-35.16.10,- Revision 2 Fire' barrier penetration seals.
control building computer rooms -
18 months PT-35.16.11, Revision'4 Fire barrier penetration seals.
diesel generator building -
18 months PT-35.16.13, Revision 6 Fire barrier penetration seals augmented'off - gas building -
18 months
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PT-34.2.2.1, Revision 4 Control building swinging fire i
door inspection - monthly The above surveillance procedures were reviewed to determine if the
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various test outlines and inspection instructions adequately implement the surveillance. requirements of the plant's Fire Projections Technical Specifications.
In addition, these procedures were reviewed' to determine if. the inspection and test instructions followed general industry fire protection practices, NRC fire protection program guidelines and the guidelines of the National Fire Protection Association (NFPA) Fire Codes. Based on this review, it appears that the above procedures are satisfactory.
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c.
Fire Protection System Surveillance Inspections and Tests The inspectors reviewed the following surveillance ir.spection and test records for the dates indicated:
PT-34.1.1.0 -
Diesel driven fire pump test -
weekly June 1, 1987, June 6, 1987, and June 15, 1987
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Electric driven fire pump functional test - monthly June 1, 1987, June 8, 1987, and June 15, 1987 PT-34.5.5 -
Diesel and electric fire pump functional test - annual October 11, 1985 and October 14, 1986 PT-34.7.1.0 -
Fire Suppression water system flow test - 3 years December 6,1983 and April 17, 1983 Pf-34.6.4.1 -
Sprinkler and spray system visual inspection reactor building Unit 1 -18 months August 15, 1986 PT-34.5.1.3 -
Unit I reactor building fire protection valve cycle and standby gas treatment deluge system test - annual
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August 15, 1986 PT-34.5.1.5 -
Diesel generation building fire protection valve cycle test -
annual July 25, 1986 and April 15, 1987 PT-34.5.1.6 -
Service water building, radwaste building, and main water treatment building sprinkler and valve cycle test - annual
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- 7 March 5,1986 and June 4,1987.
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PT-34.2.3.1 --
Hose station inspection reactor.
-building Unit 1.. monthly April 2, 1987, May 2 and June 2, 1987
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Hose rack surveillance - 18 months April 20, 1984 and November 18, 1985 P.T-35.11.3 -
Hose station operability and hose hydrostatic test - 3 years February 12, 1982 and May 3, 1985 PT.34.2.2.1 -
Control building swinging fire
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door inspection - monthly.
July 4,1986 through June 2,1987 The surveillance test record data and testing frequency associated '
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with'.the above, fire protection system surveillance test / inspections-l were'found to be-satisfactory with regard to meeting the requirements of the plant's Fire Protection Technical Specifications.
d.
Fire Protection Audit The'most recent audit report of the Brunswick Fire Protection Program-were reviewed. These audits were:
(1) Quality assurance audit report QAA/21-86-03, annual Brunswick nuclear project - operational fire protection program audit dates April 28 - May 2, 1986.
(2) Quality assurance audit report QAA/21-87-03, triennial Brunswick nuclear project fire protection program audit, audit dates April 27-30, 1987.
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These audits identified several fire protection program discrepancies and unresolved items, and recommended several program improvements.
The licensee has either implemented the corrective actions associated with these audit findings or a scheduled date for completion of the correction actions had been established.
The licensee' appears to be taking the appropriate corrective actions on these audit findings except for. the diesel generator building / detection concern identified by the triennial' audit.
The triennial audit report identified that the thermal fire detectors located in the pipe trenches in each diesel generator room as required by Section 5.8.4 of the NRC's November 22, 1977 fire protection Safety Evaluation Report (SER) were disconnected.
The
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licensee, in lieu 'of the thermal detectors, has installed an automatic'
sprinkler system with a water flow alarm in each of the~ diesel generator. room pipe trenches.
The licensee considers that the automatic sprinkler protection in the trenches exceeds the protection requirements of. Section 5.8.4 of the SER 'in that the automatic j
sprinklers. act as a detection and. as suppression _ device.
However, the audit team could not. locate any documentation'which identified this change-in the fire protection program to the NRC or. documentation indicating NRC's acceptance.of this change.
As a result of this concern, the inspectors made an inspection of the diesel generator building and the piping trenches around the diesel generators.
Based on this inspection and the. location of the.
i sprinkler heads in the trenches, it appears that if a flammable / s combustible liquid type fire were to occur within the boundarideiof.
i the trenches it is-expected that the. sprinklers would react to this fire condition and initiate ' the water flow alarm-device.
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Appendix R compliance program a fire in any single diesel gene,'s inspectors also determined that upon completion of Brunswick htor.
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cell will not preclude the plants ability to achieve and maintain' hot shutdown conditions.
The licensee has indicated that in response to
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resolving this audit issue that they will document this ci;ange with the NRC. This will be reviewed during a subsequent NRC inspection.
e.
Fire Brigade h
(1) Organization l
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The total station fire brigade is composed of approximately 88
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The on duty shift fire i
brigade leader is normally one of the Senior Reactor Operators-and the remaining four fire brigade members are composed of an auxiliary operator. The inspectors reviewed the on duty shifts-for the following dates and verified that sufficient qualified i
fire brigade personnel were on duty to meet the provisions of j
the plant's Technical Specification:
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July 26, 1987 l
July 27, 1987
July 28, 1987 S
In addition, the inspectors verified that sufficient personnel l
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were assigned to each shift to meet the minimum operating and fire brigade staff requirements of the Technical Specifications.
Therefore, it appears based on the review of the duty rosters y
associated with the above dates, that there was sufficient manpower i
l on duty to meet both the operational and the fire brigade requirements of the plants Technical Specifications.
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(2) Training.
The inspectors reviewed the training and drill records for-five brigade leaders and 13 brigade members.for the a second, third and fourth quarters'of 1985, all four quarters of 1986 and first_ and second quarter of 1987.
The records reviewed indicated that each of these leaders and members.had received an annual. medical ' review, attended the required training and participated in the required number of drills.
The inspectors also verified that a fire brigade drill had been conducted every calendar quarter for each shift for first through' the fourth quarter of.1986.and the first and second quarter of 1987. The fire brigade training records which were inspected were found satisfactory.
In addition, the inspectors reviewed the licensee's initial fire brigade training program to verify that the following training
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Indoctrination of the plant fire fighting plan with
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specific identification of each individual's responsi-
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bilities.
Identification of the type and location of fire hazards and
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essociated types of fires that could occur in the plant.
The toxic and corrosive characteristics of expected
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products of combustion.
Id.entification of the location of fire fighting equipment
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fd each fire area and familiarization with the layout of the plant, including access and egress routes to each area.
The proper use of available fire fighting equipment and the
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correct method of fighting each type of fire.
The types
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of fires should include fires in energized. electrical
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equipment, fires in cables trays, hydrogen fires, fires r
involving flammable and combustible liquids or hazardous process chemicals, fire resulting from construction or modifications (welding), and record file fires.
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emergency breathing equipment.
The proper methods for fighting fires inside buildings and
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confined spaces.
The direction and coordination of the fire fighting
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activities (fire brigade leaders only).
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Detailed review of fire fighting strategies and procedures.
Review of the latest plant modifications and corresponding
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changes in fire fighting plans..
Based. on ' this review, it appears. that the licensee's initial!
. fire brigade training program covers the above required training topics..
In. addition, it appears that the. licensee's fire brigade training program repeats the basic' fire fighting skills.
of >the initial program to qualified fire brigade members every two years.
(3)
Fire Brigade Fire Fight'ing Strategies The inspectors reviewed the following plant fire fighting strategies-(Pre-Fire Plans):
DG-1, Revision 0,-
Diesel generator building basement, Elevation 2'-0".
DG-2, Revision 0 Diesel generator building D.G. Cell 4, Elevation 23'-0".
SW-1A, Revision 0, Service water building, Elevation 20'-0".
SW-1B, Revision 0, Service water sump and.
basement, Elevations 4'-0" and 13'-4".
CB-5, Revision 0, Control Building Unit 1 cable spreading room, Elevation 23'-0".
CB-8, Revision 0, Control building battery Room 18. Elevation 23'-0".
CB-14. Revision 0 Control building, computer rooms, Elevation 49'-0".
CB-23, Revision 0, Control building control room.
Elevation 49'-0.
RB2-1-g(s), Revision 0, Reactor building, Elevation 20'-0" south, i
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RB2-10, Revision 0, Reactor building RWCU pump / heat exchanger area, Elevation f0'-0".
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Based on this review, the inspectors detennined that the above fire fighting strategies adequately addressed the fire hazards in the area, the type of fire extinguishants to be utilized, the direction.of attack, systems in the room / area to be managed in order to reduce. fire damage, heat sensitive equipment in the room / area, and specific fire brigade duties with regard to smoke control and salvage.
However, the inspectors identified that upon completion of the Appendix R fire protection modifications it may be necessary for the licenses to review and revise.certain pre-fire plans.
The licensee. indicated that they would take this under consideration.
This will be reviewed during a subsequent NRC inspection..
(4)
Fire Brigade Drill During this inspection, the inspectors witnessed an unannounced fire brigade drill.
The drill fire scenario was a fire in the Unit 2 south core spray pump room which was apparently cause by a lube. oil leak associated with the B-train core spray pump.
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Five fire brigade members responded to the pending fire energency.
The brigade assembled outside the core spray pump area in full protection fire-fighting turnout clothing and self contained breathing apparatus.. An initial size-up of the fire condition was made by the fire brigade and one 11 inch fire attack hose line-was advanced down into the pump area from reactor building Elevation 20'-0". The fire attack hose line was placed in service to protect exposed areas of the pump room
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and the fire was extinguished utilizing the water fire hose and dry chemical fire extinguishers in 30 minutes.
The fire brigade utilized proper manual firefighting methods and reacted to the fire drill scenario in an effective and efficient manner. However, the brigade did not bring any additional backup firefighting or support equipment with them to the scene of the fire.
This backup or support equipment (i.e. extra fire hose, nozzles, foam, forcible entry tools, spare air cylinders, smoke removal equipment, etc.)
may become critical during actual fire conditions.
Therefore, the logistics of backup and support equipment should be integrated into the plant pre-fire plans and fire drills.
This will be evaluated during a subsequent NRC inspection.
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(5)' Fire Brigade Administrative, Organiz.ational and Operational Procedures The inspectors Ereviewed the following procedures. which are associated with the administration, organization and operation of the plant fire brigade:
Procedures No.
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FPP-001 Revision 4 Fire protection ' program
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FPP-002 Revision 0 Fire protection records FPP-003 Revision 4 Fire brigadedrainings FPP-004 Revision 0 Fire brigade personnel medical & physical qualifications FPP-005 Revision 2 Fire watch qualifications duties and responsibi-lities FPP-006 Revision 2 Personnel protection equipment portable fire
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fighting equipment INSP inventory.
l FPP-007 Revision 2 Control E use of fire fightings. equipment-FPP-008 Revision 3 Fire house weekly equipment surveillance
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FPP-025 Revision 1 Operation of respiratory
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air compressor group FPP-031 Revision 1 Fire brigade roster 01-36 Revision 2 On-shift drills -
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operations instructions f.
Plant Tour and Inspection of Fire Protection Equipment (1)
Inspection of Fire Brigade Manual Fire Fighting Equipment The inspectors performed an inspection of the fire brigade equipment, consisting of fire hose, noz zk t, tools, and miscellaneous equipment, stored at the fire by !gade equipment response locations located in the control room complex, the
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south' fire house and the radwaste control room. The inspectors found the sets of turnout gear '(coats, boots' helmets the -
dedicated fire brigade self contained breathing apparatus, 'and spare air cylinders stored at the fire. brigade ' equipment responses locations to be properly maintained and stored-in a ready condition.
(2) Outside Fire Protection Walkdown The inspectors verified that the two water storage tanks
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contained sufficient water' to meet the requirements of the Technical Specifications.
The two fire pumps were inspected and the. diesel fire pump was out of service. ' The pump due to a packing problem was taken out of service on July 28, 1987 and the Technical Specification seven-day limiting. conditions for operation action statement was entered.
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The inspectors requested the Resident Inspectors to monitor and follow-up on the operational status of the diesel fire pump.-
The following sectional control valves in the outside fire protection water supply system were inspected and verified to be properly aligned in position:
2-FP-PIV 46 Water treatment fire protection-isolation valve 2-FP-P1V 7 Ring header isolation valve 2-FP-PIV 19 Ring header sectional valve 2-FP-PIV 47 Ring header sectional valve-2-FP-PIV 9 Reactor Building 2 standpipe supply valve The following fire hydrant equipment houses were inspected:
Hose house 11 Hose house 12 Hose house 6 Hose house 7 The equipment house contained the minimum equipment requirement of that specified by NFPR-24, Private Fire Service Mains and their Appurtenances, and/or the FSAR commitments. The eqt'ipment appeared to be adequately maintained.
A tour of the exterior of the plant indicated that sufficient clearance was provide between permanent safety-related buildings and structures and temporary buildings, trailers, and other transient combustible materials.
The general housekeeping of the areas adjacent to the permanent plant structures was l
satisfactory.
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.(3) Permanent Plant Fire P'otection Features r
A plant tour was made by the inspectors. During the plant tour, the following safe shutdown. related plant areas and their related fire protection features were inspected:-
Unit I cable spreading room, Evaluation 23'0 "
(Fire Zone CB-5)
Unit 2 cable spreading room,' Elevation 23'-0" (Fire Zone CB-6)
Unit 1 1A battery room Elevation 23'-0" (Fire Zone CB-7)
Unit 1 IB Battery room, Elevation 23'-0"
.(Fire Zone CB-9)
Control room, Elevation 49'-0" (Fire Zone CB-23)
Diesel' generator building basement, Elevation 2'-0" (Fire Zone DG-1)
Diesel Cell No.4, Elevation 23'-0" (Fire Zone DG-2)
E7 Switchgear room Elevation 23'-0" (Fire Zone DG-8)
E8 Switchgear room, Elevation 23'-0" (Fire Zone DG-9)
El switchgear room, Elevation 50'-0" (Fire Zone DG-11)
E2 switchgear room, Elevation 50'-0" f
(Fire Zone DG-12)
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E3 switchgear room, Elevation 50'-0"
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(Fire Zone DG-13)
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E4 switchgear room, Elevation 50'0 "
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Fan room, Elevation 50'-0" (Fire Zone DG-16)
Reactor Building Unit 1 RHR pump room norti, Elevation -
17'-0" (Fire Zone RB1-1C)
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Reactor building Unit 1 RHR p:mp room south, Elevation-17'-0" (Fire Zone RB1-Id)
Reactor building Unit 1 HPC1 pump room, Elevation -17'-0" (Fire Zone RB1-2)
Reactor building Unit I north central area, Elevation 20'-0" (Fire Zone RB1-Ig(NC))
Reactor building Unit I northeast corner, Elevation 20'-0" (Fire Zone RB1-Ig.(NE))
Reactor building Unit 1 east central area, Elevation 20'-0" (Fire Zone RB1-1g(EC))
Reactor building Unit I southeast conner, Elevation 20'-0" (Fire Zone RB1-Ig(SE))
Reactor building Unit I south central area, Elevation 20'-0" (Fire Zone RB1-1g(SC)
Reactor building unit I southwest corner, Elevation 20'-0" (Fire Zone RB1-Ig(SW))
Reactor building Unit I northwest corner, Elevation 20'-0" (Fire Zone RB1-1g(NW))
Reactor building Unit I north central area, Elevation 50'-0" (RB1-lh(NC))
Reactor building Unit i northeast corner, Elevation 50'-0" (Fire Zone RB1 - 1h (NE))
Reactor building Unit 1 east central area, Elevation 50'-0"
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(Fire Zone RB1-lh(EC))
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Reactor building Unit 1 southeast corner, Elevation 50'-0"
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(Fire Zone RB1-lh(SE))
l Reactor building Unit 1 southwest corner, Elevation 50'-0" (Fire Zone RB1-lh(SW))
Reactor building Unit I west central area, Elevation 50'-0"
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(Fire Zone RB1-lh(WC))
l Reactor building unit I northwest corner, Elevation 50'-0" (Fire Zone RB1-lh(NW))
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The fire / smoke detection systems, and manual firefighting equipment (i.e., portable extinguishers, hose stations, etc.)
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'for the above plant areas were inspected and verified to be in
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service except for the fire barrier assemblies separating the various plant areas into fire areas.
Currently, the licensee has established fire watches which patrol the inoperable fire barriers in the diesel generator, Unit 1 and 2 reactor, and
Unit I and 2 control buildings on an hourly basis.
The licensee i
has currently scheduled to complete the fire barrier penetration fire seals in the diesel generator building, the non-outage fire seal installations in the Unit 2 reactor building, Unit 2 control butiding and the outage fire seals in -the Unit i reactor building by the end of 1987..
The fire seals in the Unit 2 reactor building which require an outage will.be completed by
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January 31, 1988 and.the non-outage fire seal installations in I
the Unit 1 reactor building and control building will be completed by the end of 1988.
These fire seal installations along with the adequacy of the licensees fire areas and. fire barrier assemblies will be inspected during a subsequent NRC inspections.
The sprinkler systems installed in the Unit 1 cable spreading room, Unit 2 cable spreading room, diesel generator building
basement, Diesel Cell #4, diesel generator fan room, north RHR l
pump room, and the south RHR pump room and the CO2 system installed in HPCI pump room were inspected and found to be in service.
Based on this inspection, it appears that the fire protection features associated with the above plant areas are satisfactorily maintained.
The plant tour also verified the licensee's implementation of the fire prevention administrative procedures.
The control of combustibles and flammable materials, liquids and gases, and the general housekeeping were found to be very good in.the areas i
inspected.
Within the areas inspected, no violations or deviations were l
identified.
I 6.
Inspector Follow-up Items (a)
(Closed) Inspector Follow-up Item (324/84-04-03), Requires successful j
and timely resolution of the fire protection procedures rewrite. The licensee implementation of the fire protection improvement program and the fire protection procedure for the control of combustibles was found to be satisfactory. Therefore, this item i; closed.
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I (b)
Inspector Follow-up Item (325/86-30-01, 324/86-31-02), Maintenance
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of the fire pumps.
Trouble Ticket No. 85-AKLW1 implemented the corrective actions associated with the diesel fire pump seals and bearing sleeves. This work was completed on April 25, 1987; therefore, this item is closed.
7.
Licensee Event Reports (LER)
l (a)
(Closed) LER (81-118), Inoperable reactor building fire barrier penetration seals.
Currently the licensee is implementing a fire barrier seal improvement program which will evaluate the adequacy of all the fire barrier penetration seals installed in the required fire barriers. This program including all modifications is currently scheduled to be completed by the end of 1988.
This item is closed.
(b)
(Closed) LER (83-95), Inoperable fire barrier penetration seals.
See item a above for closecut.
8.
Employee Concerns
'
(a)
File No: RII-87-A-0013, Falsification of fire protection training records.
On January 26, 1987 NRC Region II received an employee concern that two of the fire brigade training instructors had signed the names on the training roster of some individuals as attending the December 29-30, 1986 fire brigade training.
The inspector reviewed the training report for the December 29-30, 1986, 8th quarter Annual Practice Firefighting Fire Brigade Training
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Session.
The inspector could not substantiate any impropriety in
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this training report.
The name of the attendees were properly typed
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on the training report roster and attendance was verified by the
instructors.
The inspector could not verify that the licensee i
violated any of their procedures which govern the documentation of attendance at a fire brigade training session or the process in which j
the fire brigade training records are maintained.
Therefore, this i
employee concern is considered closed.
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(b) File No: RII-87-A-0055, Failure to update pre-fire plans.
The inspectors reviewed a sample of the fire pre-plans (sea section 3 of i
this report) and found the information in these plans to be satisfactory with respect to current plant conditions.
However, it
should be noted that upon completion of the appendix R fire protection modifications it will be necessary to revise some of the i
existing pre-fire plans to incorporate the additional fire protection currently being installed and any supplemental fi re brigade
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operational /firefighting instructions which may be required in order to ensure the protection of one train of safe shutdown capability.
The inspector could not substantiate that the current pre-fire plans were greatly inaccurate with respect to current plant conditions.
Therefore, this employee concern is considered closed.
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