IR 05000302/1980040
| ML19341C753 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 02/09/1981 |
| From: | Conlon T, Miller W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19341C749 | List: |
| References | |
| 50-302-80-40, NUDOCS 8103040120 | |
| Download: ML19341C753 (11) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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REGION 11 101 MARIETTA ST., N.W., SUITE 3100
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Report No. 50-302/80-40 Licensee: Florida Power Corporation 320134th Street, South St. Petersburg, FL 33733 Facility Name: Crystal River Docket No. 50-302 License No. OPR-72 Inspection at Crystal River site n Crystal River, Florida I
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Inspector:
W. H. Miller, Jr.
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Date Signed Approved
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. E. Conlon, Section Chief, RC&ES Branch Date ~/ Signed Inspection on December 2-5, 1980 SUMMARY Areas Inspected This special, announced inspection involved 29 inspector-hours on site in the areas of fire protection / prevention.
Results Of the areas inspected, no items of violation or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Employees
- J. Bufe, Compliance Auditor
- J. Cooper, QA/QC Compliance Manager
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M. Harman, Site Nuclear Administrative Manager
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S. Johnson, Maintenance Staff Engineer
- W. G. Lobo, Licensing Specialist
- K. Lancaster, Compliance Supervisor
- T. Lutkehaus, Technical Services Superintendent i
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P. McKee, Operations Superintendent
- G. A. Patriss, Nuclear Fire Protection Specialist
- D. Poole, Nuclear Plant Manager
- D. Smith, Technical Support Engineering Supervisor
- Attended exit interview
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-2.
Exit Interview The inspection scope and findings were summarized on December 5,1980 with those persons indicated in Paragraph 1 above.
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3.
Licensee Action on Previous Inspection Findings Not inspected.
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4.
Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or ~ may involve violations or deviations.
New unresolved items identified during this inspection are discussed in paragraph Nos. 5.b.(2), 6.d.(1), 6.d.(2), and 6.d.(3).
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5.
Fire Protection / Prevention Commitments l
This inspection evaluated the licensee's progress and action on the fire protection commitments made to the NRC.
The NRC Fire Protection Safety
Evaluation Report (FPSER) dated July 27, 1979 supporting Amendment No. 23 to the Crystal River Unit 3 Operating License and the licensee's Fi re Protection Program Review of Crystal River Unit 3 (FPR) were used in this evaluation. These documents describe the fire protection commitments,
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- requirements and scFedule dates of implementation.
The commitments and findings are as follows:
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a.
' Commitments
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No.
Location / Modification FPSER Sec.
Status
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i Auxiliary Bldg - EL 119 5.3
(1)
Sprinkler Systems l
(IA)
Zone 1-beneath cable trays 3.27
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(18)-
Zone 5-beneath cable trays 3.27
(IC)
Zone 7-beneath cable trays 3.27 (10)
Zone 18-dry cleaning station 3.27
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(2)
Fire door (3Hr)-shop facility 3.12 Open (3)
Fire detection - Zone 3.15.a 8/81 1, 5, 7,18, 25 and 26
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Fire stops in cable trays 3.17.c 11/81
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(5)
Standpipe hose reel-relocated 3.16 Closed in waste drumming area
i Auxiliary Bldg. - El 95 5.4 (6)
Fire detection 3.15.b 8/81
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i-(6A)
Zone 4-makeup and purifi-3.29 8/81 j
cation pump rms
(68)
Zone 7-safety related hallway 5.4.6 8/81 i
(6C)
Zone 17-sea water pump room 3.15.b & 3.29 8/81 (6D)
Zone 18-nuclear service 3.15.b 8/81
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booster pump room 3.15.b 8/81
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(6E)
Zone 32 pump and tank room 3.15.b 8/81 j
(7)
sprinkler systems - Zones 1 and 5
(8)
Cable tray fire stops - zone 3.17.a 11/81
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5 and 13
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(9)
Emergency lighting Unit -
3.10 Closed i
makeup pump area l
(10)
Fire barriers - cables in 3.29 8/81
make up pump area
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(11)
Battery powered lighting 3.26 Closed
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units-zones 1, 5, 7 and 13-
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l Auxiliary Bldg. - EL 75 5.5
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(12)
Fire detection-Zones 1&2 3.15.c 8/81
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i Containment Electrical 5.6 i
Penetration Areas
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(13)
Fire detection 3.15.d 8/81 (14)
Cable tray fire stops -
3.17.b 11/81 instrumentation cables between channels A&B Intermediate Bldg - EL 119 5.7 (15)
Fire detection 3.15.d 8/81 (15A)
Pressurizer control cabinet area (158)
Containment personnel access area (15C)
Zone 1 (150)
Zone 4
(16)
Sprinkler systems Zone 5-transient materials Intermediate Bldg - EL 95 5.8 (17)
Fire detection - steam driven 3.15.e 8/81 AFWP (18)
Fire barrier (1-Hr) -
3.18
(18A)
Cable trays above AFWP (18B)
Motor operated values Reactor Bldg 5.9 (19)
Fire detection 3.15.f 8/81 (19A)
RCP (19B)
Ventilation Units (19C)
Cable concentrations (20)
Cable fire stops - 95 3.17.c 11/81 119' EL (21)
Standpipe system 3.5 11/81 Control Room 5.10 (22)
Combustible storage 3.19.1 Closed (23)
Remove stove 3.19.2 Closed (24)
Fire door / closure and latch 3.19.3 Closed (25)
Fire extinguisher - Class A 3.9 Closed Cable spreading room 5.11 (26)
Halon system - reserve supply 3.7 Open (27)
Recirculation fans / essential 3.8 Open power (28)
Floor - fire rated (1-Hr)
3.14 6/81 Battery Rooms 5.13 (29)
Relocate exhaust ducts to 3.20 Closed ceiling (30)
Monitor ventilation flow 3.20 Open Diesel Generator Rooms 5.14
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(31)
Curbs at doorways 3.21.1 Closed (32)
Floors drain modifications 3.21.2 Closed (33)
Smoke detector in control 3.21.3 Closed room - relocate (34)
Sump - fuel flow alarm 3.21.4 Closed Turbine Bldg 5.15 (35)
Wall openings into 3.13 Open
Intermediate Bldg upgraded to 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> fire rating
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General Plant Areas e
(36)
Fire pump house - floor drain 3.3 Closed (37)
PIV - guards 3.4 Closed
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(41)
Control Valve supervision 4.3 Open (42)
Drip protection for 3.6
electrical equipment in sprinklered areas (43)
Fire detection system -
3.2
emergency power. supply (44)
Fire alarm unsupervised 3.22 Closed
circuits - tested monthly (45)
Portable radios for fire 3.11 Closed brigade /2 units (47)
Safe shutdown systems 3.1
3.25 3.27 3.28 3.30 Notes: * Refer to paragraph 5.b for comments.
"Open".
Item contains deficiencies. Refer to paragraph 5.b for details.
" Closed".
Item appeared satisfactorily completed based on plant tour and randum review of construction documents.
i Dates indicate schedule completion date.
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b.
Findings i
Additional information on the "open" items and items marked with "*" is listed below.
The below listed numbers correspond to the numbered items in Paragraph 5.a.
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(1) The licensee was advised by NRR's letter of October 14, 1980 i
(letter from R.
W.
Reid, Chief Operating Reactors Branch #4, Division of Licensing, NRR to J. A. Hancock, Director, Nuclear
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Operations, FPL) that the installation of automatic sprinkler systems for protection of redundant safety related cables and equipment was not adequate due to the possible thermal lag of
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j sprinkler systems.
The licensee is currently reevaluating this position. This item remaining outstanding prior to the installa-tion of the sprinkler systems.
(2) Double swinging type fire doors have been installed but hardware
is not properly adjusted to permit doors to automatically close.
Also, it appears that one door is equipped with the wrong type
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hardware. Manual ' latching type hardware is provided for one door in lieu of automatic type latching hardware which is required if
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doors are to be arranged for automatic closing.
The licensee is evaluating this item to determine the appropriate corrective action; therefore, this item is identified as Unresolved Item (302/80-40-01),
inadequate fi re door hardware, and will be reviewed during a subsequent NRC inspection.
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( 7) Refer to above item (1).
(16) Refer to above item (1).
(18) Licensee also was advised by NRC's October 14, 1980 letter that
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these proposed modifications were not acceptable. The licensee is i
reevaluating NRR's response prior to taken any further action on
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this item. This item remains outstanding.
(26) Two of the 11 reserve halon cylinders were not in service due to j
missing parts to the initiation / actuation devices.
The main
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cylinders were in service and 9 of the 11 reserve cylinders could have been activated if needed.
This item will be reinspected d
during a subsequent NRC inspection.
j (27) Refer to above paragraph (18).
(30) Air flow indicators for-the battery rooms were functionally tested
and witnessed by the inspector.
The indicator for battery room
"A" failed to operate. The licensee has issued work request No.
20371-to accomplish necessary repairs to this device.
This item will be reviewed during a subsequent NRC inspection.
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(35) The fire doors from turbine building into the control building were all found in the closed position but the manual latching
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i devices on most of the inactive doors were not in the latched position.
This type hardware may not be suitable for tnis application.
This item is another example of Unresolved Item (302/80-40-01),
Inadequate fire door hardware, and will be reviewed during a subsequent NRC inspection.
The fire door dampers installed in the drainage scuppers between
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the turbine and intermediate buildings do not appear to be i
properly installed.
However, manufacturers drawings were not available to confirm the adequacy of this installation.
The licensee agreed to obtain necessary construction and installation
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documents and to consider conducting a comprehensive inspection of these dampers as well as other dampers located throughout the plant to determine if the dampers are properly installed.
The licensee is to advise the NRC Regional Office prior to February 15, 1981 as to the schedule for accomplishing this inspection.
This item is identified as Inspector Followup Item (302/80-40-02),
Licensee's inspection and evaluation of fire damper installations, and will be reviewed during a subsequent NRC inspection.
(41) The methou of supervising fire protection control valves does not appear to meet the provisions of NFPA-26, Supervision of Water Supply Valves, section 3 and 6,
This item will be reviewed during a subsequent NRC inspection.
(42) This item will not be accomplished unless the automatic sprinkler systems are provided.
(43) Refer to above item (18).
(47) This item is currently being reviewed by NRR.
Within the areas examined no apparent items of violation or deviations were identified.
6.
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a.
Fire Protection / Prevention Administrative Control Procedures The licensee's fire protection procedures for the fire brigade organization and training, control of combustible and flammable materials, control of open flame ignition sources, and fire reporting and fire fighting strategies were reviewed by the inspector.
These procedures were found to meet the NRC guidelines indocument entitled
" Nuclear Plant Fi re Protection Functional Responsibilities, Administrative Controls and Quality Assurance" dated June 14, 1977, except for the following items:
(1)
Fire Fighting Strategies Complete and comprehensive fire fighting strategies are currently being developed for the licensee by a consulting fire protection firm (Professional Loss Control, Inc.).
The final draf t of the strategies is to be reviewed by the licensee during December 1980 with document completion scheduled for February 1981.
(2) Smoking Restrictions The smoking restrictions for radiation controlled areas are included in the licensee's procedures but the precedures do not
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address smoking restrictions for other safety related areas of the
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plant. Letter file code No. 3-0-34 dated December 4,1978 to the
plant staff provided some restrictions on smoking areas in the plant, but these had not been incorporated into the plant procedures.
The licensee agreed to consider a revision to pro-
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cerdure No. EM-101, Emergency Plan Procedure, which would identify the safety areas in the plant in whch smoking would be prohibited i-or permitted.
(3) Welding, Cutting and Grinding Opertions
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Procedure CP-118, Fire Prevention Work Permit Procedure assures
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i that the hazards associated with welding, cutting and grinding operations conducted outside of. maintenance shop are adequately safeguarded. This procedure deviates from the NRC fire protection guidelines and the criteria of National Fire Protection Association (NFPA)
Standard
'No.
518, Welding and Cutting Processes, in that the hazard area is considered to extend from
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i the operation a distance of 20-25 feet whereas the NRC guideline and Section 4 of NFPA-51B considers the hazard area to extend a
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i radius of 35 feet from the operations.
The licensee agreed to review the procedure to determine if the procedure should be
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revised to meet the general industry practices.
These discrepancies are identified as Inspector Followup Item
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(302/80-40-03), fire protection administrative procedures do not meet NRC guidelines, and will be reviewd during a subsequent NRC inspection.
b.
Fire Protection Equipment
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The following surveillance inspection and test documents were reviewed by the inspector and discrepancies were noted:
(1) SP-190, Channel Functional and Circuitry Operability of Fire
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Detection Instrumentation (Monthly)
September 10, 1979 to November 5,1980. No discrepencies noted.
l (2) SP-363, Fire Protection System Tests (18 Months)
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December 1,1980 and June 7,1980. No discrepancies noted.
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(3) SP-364, Hose Station Inventory and Hydrant Operability Test l
(Monthly)
January 26, 1980 to October 25, 1980. No discrepancies noted.
(4) SP-365, Fire Pump Operability (Monthly)
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December 7,1979 to October 16, 1980. No discrepancies noted.
l (5) SP-366, Fire System Annual Valve Surveillance l
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o April 14,1979 and April 10, 1980. No discrepancies noted.
(6) SP-404, Fire Deluge and Sprinkler System Surveillance (18 Months)
i May 4, 1979. No discrepancies noted.
(7) SP-407, Fire Barrier Penetration Seals (18 Months)
i March 2, 1979. No discrepancies noted.
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(8) SP-411, Fire Protection, Deluge and Sprinkler System Tests (18 Months)
April 18, 1977 to September 18, 1978.
The tests scheduled for Septenber 1979 were not completed until September 18, 1980 or
twelve months beyond the required frequency. This occurrance was
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. reported to NRC Region II by Special Report 80-2. A Surveillance Program _ Clerk position has been initiated to help assure that the i
required surveillances are accomplished within the specified frequency.
No additional discrepancies were noted by the
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inspector.
(9) SP-501, Halon System Functional Test (Semiannually)
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September 16, 1978 to March 26, 1980.
No discrepancies noted.
However, refer to above paragraph 5.b.(26).
(10) SP-606, Diesel Fire Pump Engine Inspection and Maintenance (18 Months)
l May 18,1979 to April 25, 1980. No discrepancies no.ted.
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(11) SP-607, Fire Damper Inspection (Annual)
October 29, 1979. No discrepancies noted; however, refer to above paragraph no. 5.b.(35).
(12) AP-805, Surveillance of Plant Fire Doors (Monthly)
January 9, 1980 to August 12, 1980.
No discrepancies reported Refer to above paragraph no. 5.b.(35).
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c.
Fire Brigade Manning The fire brigade manning assignments for the following shifts were reviewed by the inspector:
Date Shift (Hrs)
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November 18, 1980 0000 - 0800 November 20, 1980 0000 - 0800 November 21, 1980 0000 - 0800 November 26, 1980 0000 - 0800 November 30, 1980 1600 - 2400 i
December 1, 1980 0000 - 0809 December 4,1980 0800 - 1600 For these shifts 5 personel were assigned fire brigade duties and at least 5.
additional qualified personnel were available for plant operations as required by the Technical Specifications.
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d.
Plant Tour A tour was made of the plant by the inspector to review the modifica-tion identified in above paragraph 5.a, to assure that the fire pro-tection systems required by Technical Specification were in service, and to evaluate the effectiveness of the implementation of the fire protection administrative control procedures.
(1)
Fire Protection Equipment
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The following fire protection equipment was inspected:
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(a)
Fire pumps (b) sprinkler systems - diesel generator rooms AHFL units 1, 2A -
20, 4A, and 48.
(c)
Interior fire hose systems (d) Halon system for cable spreading room (e) Hydrant hose house Nos. 2, 3 and 5 (f)
Fire detection system These systems were found in service, except for the reserve halon cylinders for the cable spreading room which are discussed in above paragraph 5.b.(26).
It was also noted that the sprinkler system piping supply for the AHFL (charcoal filters) units in the auxiliary building and the interior fire hose system for the auxiliary building are both supplied from the same piping system.
This arrangement does not conform to the guidelines of NRC's Branch Technical Position 9.5-1, Appendix A, Fire Protection Program for single failure criteria.
Section 5.3.3.2 (page 5-25) of the FPR states that
" independent connections are provided to the fire main loop---for manual hose station standpipes and deluge systems in the Auxiliary Building".
Section 6. A.4 (page 6-2) of the FPR states that "no single failure can.esult in loss of protection of both primary and backup fire suppression capability." However, drawing Figure 5-11 1 FPR indicated cnly a single water supply to the auxiliary building standpipe and sprinkler systems and Section 6.E.3 of the FPR states that a separate heater in the Auxiliary Building
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supplies charcoal filter deluge systems and hose stations." The
licensee is to evaluate this item and is to provide the NRC -
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Region II office the results of this evaluation.
This item is identified as Unresolved Item.(302/80-40-04), Fire suppression
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systems.for auxiliary building do not meet single failure criteria.
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Fuel Storage Areas i
Presently, a fire detection system is not provided for the fuel storage areas of the plant. Section 6.F.12 & 13 (pages 6-18) of
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the FPR states that "this area will be equipped with appropriate fire detection capability." However, the fire safety evaluation of these areas in the FPR does not state that fire dtection will t-mvided.
Section 5.1 and 3.0 of the FPSER do not require j
tic fire detection to be provided for this areas. A minor
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...uderate quantity of combustibles which are inherent to fuel i
storage areas were noted in the area by the inspector. Therefore, it appears that fire detection should be provided in these areas.
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This item is being forwarded to NRR for evaluation and is identi-fied as Unresolved Item (302/80-40-05), Automatic fire detection
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not provided for new and spent fuel areas, and will be reviewed i
upon completion of NRR's evaluation.
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(3)
Intermediate Building
Two floor openings between elevations 95 and 119 feet were noted
i by the inspector to be provided with automatic fire dampers which a<e activated by smoke detectors. These floor openings are above
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and adjacent to the motor driven and turbine emergency feea pump.
i Cable trays containing channel A safety related cable are located
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i at the ceiling level of the 95 foot elevation and cable trays containing channel B safety related cables are located on the 119 foot elevation directly over the above mertioned floor openings.
In addition, a number of other unprotected floor openings, such as pipe penetrations and openings next to containment wall, exists in the floor which separates these two fire areas.
The licensee is to review this area to determine if these unprotected floor
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openings are required to be sealed. This item is identified as Unresolved Item (302/80-40-06), Unprotected fire barrier pene-trations in the intermediate building, and will be reviewed upon completion of the licensee's evaluation.
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Within the-areas examined no apparent items of violation or deviations were detected.
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