IR 05000348/1988013
| ML20154G958 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 05/10/1988 |
| From: | Conlon T, Wiseman G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20154G946 | List: |
| References | |
| 50-348-88-13, 50-364-88-13, IEIN-84-92, NUDOCS 8805250175 | |
| Download: ML20154G958 (10) | |
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[p0 sto UNITED STATES
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NUCLEAR REGULATORY COMMISSIOM
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R EGION 11
- j I,8 101 MARIETTA STREET.N.W.
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Report Nos.: 50-348/88-13 and 50-364/88-13 i
Licensee: Alabama Power Company l
J 600 North 18th Street
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Birmingham, AL 35291-0400 l
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Docket Nos.:
50-348 and 50-364 License Nos.:
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Facility Name:
Farley 1 and 2
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Inspection Conducted: April 4-8, 1988
Inspector:
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G. R.,W'Jeman,
Date Signed
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j Approved by:
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/ #[ibf T. E. Conlon, Section Chief 7 ate Signed
Engineering Branch i
Division of Reactor Safety l
SUMARY
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Scope:
This routine, unannounced inspection was in the areas of fire protec-k tion and prevention.
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i Results:
One deviatioit was identified - Designated Combustible Storage Area i
Not Separated From Safe Shutdown-related Areas by Approved Fire Walls -
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Paragraph 5.h.(2).
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l 8805250175 880513 PDR ADOCK 05000348
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REPORT DETAILS
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1.
Persons Contacted
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Licensee Employees i
- C. L. Buck, Supervisor, Plant Modification Department j
- J. P. Hayes, Plant Fire Protection Staff
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j R. Hendley, Plant 1 raining Instructor
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- R. H. Marlow, Technical Supervisor
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- 0. N. Morey, Assistant General Manager - Operations
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- C. D. Nesbitt, Technical Manager
- J. K. Osterholtz, Unit Supervisor - Operations
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- L. M. Stinson, Manager - Modifications
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- F. G. Watford, Fire Marshall i
- R. Wiggins, Supervisor Operations Training j
- J. D. Woodard, Plant General Manager i
NRC Resident Inspectors
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- W. H. Bradford
- W. H. Miller i
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- Attended exit interview I
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- Participated in telephone exit interview on April 20, 1988 2.
Exit Interview
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The inspection scope and findings were summarized on April 8,1988, with those persons indicated in paragraph 1 above.
The ins)ector described the
areas inspected and discussed in detail the inspection findings.
On
April 20, 1988, additional discussions relating to the inspection were
held between members of the licensee's staff and the inspector.
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following new item was identified during this inspection
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Deviation (348/88-13-01), Designated Combustible Storage Area Not l
Separated From Safe Shutdown related Areas by Approved Fire Walls -
J Paragraph 5.h.(2).
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The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspection.
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Licensee Action on Previous Enforcement Matters j
This subject was not addressed in the inspection.
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Unresolved Items i
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Unresolved items were not identified during this inspection.
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5.
FireProtection/PreventionProgram(64704)
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Fire Prevention / Administrative Control Procedures The following procedures were examined by the inspector:
Procedure No.
Title FNP-0-AP-35 General Plant Housekeeping (Revision 14)
and Cleanliness FNP-0-AP-37 Fire Brigade Organization (Revision 8)
FNP-0-AP-38 Use of Open Flames (Revision 8)
FNP-0-AP-39 Fire Patrol and Watches (Revision 8)
FNP-0-AP-45 Farley Nuclear Plant (Revision 8)
Training Plan FNP-0-A0P-29.0 Plant Fire (Revision 6)
These procedures comply with the NRC supplemental guidelines of the document entitled "Nuclear Plant Fire Protection Functional Respon-sibilities, Administrative Controls and Quality Assurance" dated June 14, 1977, except a discrepancy was noted on the identification of plant rooms Unit 1, 403, Hot Instrument Shop and Unit 2, 2403, Respirator Storage Room between procedure FNP-0-A0P-29.0 and FNP-0-AP-35.
The licensee corrected the discrepancy during the inspection through issuance of Revision 7 of
)rocedure FNP-0-A0P-29.0, dated April 7, 1988, which correctly icentified these areas as to their current occupancy, b.
Fire Protection Surveillance Procedures The inspector examined the following selected fire protection surveillance procedures:
Procedure No.
Title FNP-0-STP-51.0 (Rev. 0)
Water Storage Systems Supply Check FNP-0-STP-52.1 (Rev. 7)
1A Diesel Fire Pump Operability Test
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Procedure No.
Title (cont'd)
l FNP-0-STP-56.0 (Rev. 11)
Fire System Valve
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Operability Test
I FNP-0-STP-59.0 (Rev. 8)
Visual Inspection of New or
Repaired Fire 8arrier
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FNP-0-STP-127.0 (Rev. 18)
Yard Loop - i4onthly
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f FNP-0-STP-132.0 (Rev. 2)
Hydrant Hose House
Inspection - Monthly
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FNP-0-STP-626.1 (Rev. 7)
Diesel Generator Building Heat detectors -
l Thermostats Functional Test i
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FNP-0-STP-626.0 (Rev. 12)
Reaction Sprinkler System - 18 Month Test l
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The above surveillance procedures were reviewed to determine if
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the various test outlines and insps. tion instructions adequately
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implement the surveillance requirements of the plant's fire
i Protection Technical Specifications.
In addition, these procedures
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were reviewed to determine if the inspection and test instructions I
l followed general industry fire protection practices, NRC fire
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protection program quidelines and the guide'ines of the National Fire
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Protection Associat'on (NFPA) Fire Codes.
Based on this review, it
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appears that the above procedures are satisfactory, t
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Fire Protection System Surveillance Inspections and Tests The inspector reviewed the following surveillance inspection and test
records for the dates indicated:
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Procedure No.
Results Reviewed
j FNP-0-STP-127.0 October 1987 to March 1988 j
FNP-0-STP-132.0 July 1987 to January 1988 i
FNP-2-STP-126.0 October 1987 to February 1988
2 FNP-2-STP-626.0 June 1985 and December 1986
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The surveillance test record data and testing frequency associated with the above fire protection system surveillance tests / inspections
were found to be satisfactory with regard to meeting the requirements
j of the plant's Fire Protection Technical Specifications, i
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Reports on Fire Prevention Activities The inspector reviewed the station's quarterly fire prevention
activities reports for the fourth quarter 1985, and all of 1986, and 1987.
These reports are designated in fire protection administrative Procedure FNP-0-AP-35.
These reports indicated that there were two t
incidents of fire onsite % 1986, one fire event in 1987, and two fires so far in 1988.
Of the fire events indicated, two were grass fires, one was equipment failure, and the remaWer involved welding l
or cutting activities.
None of the fire events reviewed appeared to beofmajorsafetysignificance, l
i e.
IE Information Notice No. 84-92 IE Information Notice 84-92, Cracking of Flywheels on Cummins Fire Pump Diesel Engines, was issued on December 17, 1984.
This Notice alerted licensees of a potential problem of cracking flywheels on
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l certain models of Cummins diesel engine driven fire pumps.
Cummins I
diesel engine Model No. NT-855-F2, manufactured by Peerless Pump i
Company and equipped with flywheel Part No. 3453, has experienced repeated fatigue crackings of the flywheels.
The licensee stated that a review had been performed by the FNP Maintenance Department and it was determined that FNP uses Cummins engine model Nos. NT-380-1F and NT-355-F2 diesel driven fire pumps with flywheel Part No.
BM 69576.
Therefore there are no diesel fire pumps onsite with the flywheelidentifiedIntheIEN.
This determination was documented by Memorandum No. FNP-85-1231 dated January 13, 1986.
The inspector verified the fire pump model numbers during the inspection which validated the licensee s determination.
f.
Fire Protection Audit The most recent audit reports of the Farley Fire Protection Program were reviewed.
These audits were:
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Nuclear Mutual Limited (NHL) Insurance Audit of December 17-19,
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1986.
j Annual Fire Protection Audit of July 6-9, 1987.
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The July 1987 Annual Fire Protection Audit was conducted by an outside Fire Protection Firm, Professional Loss Control (PLC) in compliance with Section 6.5.2.8.i of the FNP Technical Specifica-tions.
The audit identified eleven fire protection program enhance-ments.
The inspector expressed concern that several recommendations related to Appendix R Fire Protection features remained under evaluation and were open as indicated by the Fire Protection Punchlist.
These issues included the operability requirements and J
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i surveillance procedures for Appendix R cable fire wraps (Section
4.1.3 of PLC Audit Report); preaction sprinkler system valves for
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safe shutdown areas left in non-normal (tripped open) position
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j because of numerous fire detector spurious s'gnals (Section 4.3.1 of PLC Audit Report)its (Section 4.3.3 of PLC Audit Report.and procedur
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emergency lighting un At the
exit interview the inspector indicated his concurrence w th the
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auditor's report that management should primarily concentrate efforts
on improving the fire detection system and fire protection surveil-lance procedures in these areas.
The licensee's stated position was l
i that adequate management attention was being placed in this area.
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These items will be reviewed during future NRC inspections.
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Fire Brigade l
(1) Organization
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The total station fire bri ade proximately 154 l
personnel from the operatfons,is composed of afant chemistry security and a
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staff.
The on duty shift fire brigade leader is normally one of
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i the shift foremen and the remaining four fire brigade members are composed of two plant operators, one security officer and
,l one person from the chemistry group.
An auxiliary bri ade composed of 58 personnel from the mechanical, electri a1
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instrumentation, warehouse and operations departments is also
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It appears that sufficient manpower is available to (
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l the plant's Technical Specifications.
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(2) Training i
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The inspector reviewed the training and drill records of ten i
i brigade members for 1987.
The records reviewed indicated that l
each of these leaders and members had attended the required
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l training and participated in the required number of drills.
The i
fire brigade training records which were inspected were found i
j satisfactory.
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The inspector reviewed the shift fire brigade drills conducted during 1987 and noted that 26 drills were conducted.
Seven i
drills were conducted in each of the first and second quarters,
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and six drills in each of the third and fourth quarters.
This i
review revealed that drills are conducted on the required basis
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Plant Tour and Inspection of Fire Protection Equipment
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(1) Outside Fire Protection Walkdown i
The inspector verified that the two fire protection water
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storage tanks contained sufficient water to meet the require-ments of the Technical Specification.
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The three fire pumps were inspected and the diesel engine fire Pump No. 2 was out of service due to problems with the pump
relief valve.
The system jockey pump and electric motor fire (
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Pump No. 3 were running and diesel engine fire Pump No. I was in
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standby.
The following fire protection valves within the fire pump house
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for fire pump alignment were inspected and verified to be
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j properly aligned as designated in Procedure FNP-0-STP-56.0:
Engine driven fire Pump No. I suction N1P43Y005
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isolation valve No. I fire tank to jockey pump suction N1P43Y109
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valve N1P43V005 Engine driven fire Pump No I suction
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N1P43V108 Jockey pnmp suction isolation valve
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i N1P43V007 Motor driven fire Pump No. 3 suction
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isolation valve Motor driven fire Pump No. 3 manual N1P43V017
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recirculation valve l
l N1P43V010 Motor driven fire Pump No. 3 discharge
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isolation valve i
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The following sectional control valves in the outside fire protection water supply system were inspected and verified to be properly aligned in position:
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N1Y43V001 Cooling tower header isolation valve
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N1Y43V002 Plant loop header isolation valve
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l N1P43V001 Storage tank No. 1 isolation valve
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N1P43V037 Yard main supply header isolation valve
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N1P43V038 Yard main supply header cross connect
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valve N1Y43V047 Unit 1 Auxiliary Building header
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j isolation valve i
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N1Y43V045 Unit 1 Auxiliary Building motor i
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operated isolation valve
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The following fire hydrant equipment houses were inspected:
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Hose house 15 Hose house 21 Hose house 46 l
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The equipment hose houses contained the minimum equipment I
requirement of that specified by NFPA-24, Private Fire Service
Mains and their Appurtenances, and/or the FSAR commitments.
The
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equipment apoeared to be adequately maintained, except it was i
noted that hase house No.15 northeast of the Auxiliary Building
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leaked rain water inside onto the fire equipment such that rust j
deposits had formed onto firehose and nozzle threads.
These i
deposits may cause difficulty in thread engagement during fire l
hose deployment.
The inspector identified this condition to the
fire protection staff who acknowledged that corrective action
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would be taken.
This will be reviewed during a future NRC j
inspection.
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A tour of the exterior of the plant indicated that sufficient clearance was provided between permanent safet
buildings and structures and temporary buildings, y-related trailers, and (
other transient combustible materials.
The general housekeeping of the areas adjacent to the permanent plant structures was j
satisfactory.
(2)
Inside Plant Tour l
A plant tour was made by the inspector.
During the plant tour
selected safe shutdown related plant areas and combustible (
storage areas as designated in Table 1 of Procedure FNP-0-AP-35 t
and FSAR Section 98 within the Unit 1 and Unit 2 Auxiliary j
Buildings and Diesel Generator Building were inspected.
The fire / smoke detection systems, manual firefighting equipment
(i.e., portable extin area boundary walls,guishers, hose stations, etc.) and the fire j
floors and ceiling associated with the
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above plant areas were inspected and verified to be in service i
or functional; except it was noted that Room 444, Clean Linen Storage, as designated in Table I of the Farley housekeeping i
procedure FNP-0-AP-35 was being utilized as a general combus-
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tible storage area.-
In addition, it was noted that one-hour fire wrapped safe shutdown cable raceways 21E044, 31E021, and
41E020 as identified in Section 98.B-41.2 of the FSAR were
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routed through Room 444 in the concealed space above the
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I suspended ceiling.
The inspector expressed concern that no i
sprinkler coverage was provided for the safe shutdown cable raceways in Room 444 and the room's partial height separation walls were not approved rated fire walls for a designated combustible storage room.
During the exit interview the licensee stated that this Unit 1 plant area was undergoing
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outage modifications related to PCN-85-1-3431 and that l
additional information from the offsite Nuclear Engineering and
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Licensing's(NEL) organization would be required to resolve the inspector concerns.
During a telephone conversation on l
April 20, 1988, the licensee stated that during NEL's followup l
evaluations for Room 444 following this inspection an hourly fire watch patrol was established for the area and the detection
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system was verified operable as a compensatory Technical Specification compensatory measure.
The licensee stated that further cable interaction evaluations by NEL verified that cables within the wrapped raceways in Room 444 are no longer required for safe plant shutdown.
The licensee stated that the plant modification had, however, downgraded the partition walls of Room 444 such that at the time of the inspection, they were not approved rated walls.
This condition does not conform to the commitments made to the NRC in Section 98.2.2.2 of the
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Farley FSAR.
This discrepancy is identified as Deviation (348/88-13-01), Designated Combustible Storage Area Not Separated From Safe Shutdown-related Areas by Approved Fire Walls.
The licensee representative acknowledged this finding during the telephone conversation of April 20, 1988.
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The automatic preaction systems installed in safe shutdown areas of the Auxiliary Building were inspected.
The inspector expressed concern that Technical Specification systems 2A-23 (West Cable Chase), 2A-43 (Cable Spreading Room) and 2A-59 (West Corridor) were placed in an abnormal "tripped" configuration.
While the status of the preaction deluge valves do not reduce the system's ability to flow water to control fires which might occur, the abnormal condition of the systems results in the loss of supervisory signal service for the sprinkler piping as well as loss of water flow alarms in the event of pipe break or sorinkler actuation which could cause serious damage to sensitive electrical equipment in the protected areas.
The licensee's staf f provided the inspector copies of Plant Change Requests (PCR) Nos.81-960 and 83-2-2501 approved by the plant manager on December 19, 1983, which identified this issue and
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requested resolution by the off-site design organization.
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the time of the inspection no resolution had been implemented.
This item was previously identified during the 1987 annual fire protection audit and is discussed in Paragraph 5.f. of this report.
Other than noted above, the fire protection features astociated with safe shutdown plant areas inspected appeared functional, j
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s The plant tour also verified the licensee's implementation of Je fire prevention administrative procedures.
The control of combustibles and flanmable materials, liquids and gases, and the general housekeeping were found to be good in the areas inspected.
A welding operation was observed in Room 185 of the Auxiliary Building.
An approved "Hot ' Work" permit had been issued for the welding operation and work practices met the
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. licensee's fire prevention control procedures.
(3) Appendix R Fire _ Protection Features The inspector visually inspected the fire rated raceway fire barriers required for compliance with Appendix R,Section III.G.2 in the following plant areas:
Raceways No.
Location BDDAIB Room 185 Unit 1 Auxiliary BHDE09 Building 100 ft. Elevation Component Cooling Water Room BEE 010 Room 319 Unit 1 Auxiliary BHLZ45 Building 139 ft. Elevation Hallway 21E044 Room 444 Unit 1 Auxiliary 31E021 Building 151 ft. Elevation 41E020 Clean Linen Storage BHD15C Room 2185 Unit 2 Auxiliary Building 100 ft. Elevation; Component Cooling Water Room'
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BHF443 Room 2319 Unit 2 Auxiliary B10030 Bid' ding 139 ft. Elevation,
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Ha,1way
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AHE321 Room 2-502 Auxiliary BHJ12W Building, Stairwell dased on the inspector's observation of the above raceway fire barrier enclosures, it appears that the one hour fire barrier integrity associated with the above fire barrier assemblies was
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complete.
Except as noted above, within the areas inspected no additional violations or deviations were identified.
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