IR 05000302/1981025
| ML20042B715 | |
| Person / Time | |
|---|---|
| Site: | Crystal River |
| Issue date: | 12/03/1981 |
| From: | Conlon T, Miller W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20042B668 | List: |
| References | |
| 50-302-81-25, NUDOCS 8203250571 | |
| Download: ML20042B715 (1) | |
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UNITED $TATES
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NUCLEAR REGULATORY COMMISSION o
REGION ll 101 MARIETTA ST., N.W., SUITE 3100 o,%
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ATLANTA, GEORGIA 30303
Report No. 50-302/81-25 Licensee:
Florida Power Corporation P. O. Box 14042, Mail Stop C-4 St. Petersburg, FL 33733 Facility Name: Crystal River Docket No. 50-302/81-25 License No. DPR-72 Inspection at Crystal River site near Crystal River, Florida Inspector:
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W. H. Miller, Jr. /
i Date Signed Approved by C M W
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T. E. Conlon, Section Chief Date Signed Engineering Inspection Branch Engineering and Technical Inspection Division SUMMARY Inspection on November 17-20, 1981 Areas Inspected This routine, unannounced inspection involved 27 inspector-hours on site in the areas of fire protection / prevention.
Results Of the areas inspected, one violation was found (Non-functional fire door between hot machine shop and auxiliary building - Paragraph 7.d) and no apparent devia-tions were found.
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PDR ADOCK8203250571 820318 05000302 G
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REPORT DETAILS
1.
- Persons Contacted Licensee Employees
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- D. C. Poole, Nuclear Plant Manager
- G. Boldt, Technical Services Superintendent
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- J. Cooper, QA/QC Manager
- K. F. Lancaster, Sr. Quality Program Auditor
- C, Brown, Nuclear Compliance Supervisor
- J. Cuneo, Nuclear Technical Training Supervisor
- J. Dillon, Nuclear Plant Engineer S. Robinson, Nuclear Plant Engineer G. Williams, QA/QC Supervisor -
D. Fields, MAR Specialist
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R. Carbiener, QC Inspector
- G. Patrissi, Nuclear Fire Protection Specialist Other Organizations
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R. Arthur, Electrical Engineer Supervisor / Catalytic
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R. W. Laxton, Electrical Supervisor / Catalytic
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NRC Resident Inspector
- T. Stetka
- Attended exit interview
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2.
Exit Interview
The inspection scope and findings were summarized on November 20,- 1981 with those persons indicated in paragraph 1 above.
3.
Licensee Action on Previous Inspection Findings a.
(Closed) Unresolved Item (302/78-11-04) - Improper Storage of Flammable and Combustible Liquids in Turbine Building: Approved flammable liquid
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storage cabinets and safety cans have been provided for the storage of
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flammable and combustible liquids. The licensee's procedure, EM-101, l
Fire Protection Plan, Section 6-2 provides adequate provisions to help control the storage of combustibles. This item is closed.
b.
(Closed) Deviation Item (302/79-52-01) - Lack of Procedure Conformances to NFPA-10 for Inspection of Portable Fire Extinguishers:
The licen-see's procedure SP-800, Monthly Portable Fire Extinguisher Inspection, 1 -
has been revised to include the essential requirements of NFPA-10.
i Also procedure SP-801, Portable Fire Extinguisher Yearly Maintenance
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Inspection, has been issued to assure that all extinguishers receive the required annual maintenance. This item is closed.
c.
(0 pen) Unresolved Item (302/80-40-01) - Inadequate Fire Door Hardware:
A work order has been issued to provide new approved type hardware on the fire doors,between the hot machine shop and the auxisiary building and between the turbine building and control building. Presently, the hardware to these doors are broken. and the doors will not automatically close and properly latch. The. nonfunctional, doors between the turbine and control buildings are not considered a violation since these doors do not separate safety related areas but these doors are important to safety and need to be repaired. However, the. inoperative doors between-the hot machine shop and the auxiliary building are required to be operable by the Technical Specifications.
This item is a violation.
Refer to paragraph 7.d for details.
d.
(0 pen) Unresolved Item (302/80-40-04) Fire Suppression Systems for Auxiliary Building Do Not Meet Single Failure Criteria: As previously advised by FPC's letter of February 13,1981 (File 3-0-3-a(2), 3-F-2)
from J. A. Hancock to James P. O'Reilly, NRC Region II, a design is in process to provide an additional water supply for the auxiliary building. This item remains open.
e.
(Closed) Unresolved Item (302/80-40-05) - Automatic Fire Detection Not
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Provided for New and Spent Fuel Areas: NRR has reevaluated this item l
and advised by telephone conversation between R. K. Anano, NRC/NRR and W. H. Miller, NRC Region II that automatic fire detection for this area was not required due to the low level of combustible storage and high ceiling heights. Therefore, this item is closed.
f.
(Closed). Unresolved Item (302/80-40-06) - Unprotected Fire Barrier Penetrations In The Intermediate Building.
The licensee has-reeval-uated the fire protection features in this area and determined that these openings are not required to be covered or sealed due; to the low quanity of combustibles located in this area, the smoke detector system being installed in this area and the availability of manual fire fighting equipment. Therefore', this item is closed.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
. Inspector Followup Items a.
(Closed) Inspector Followup Item (302/78-11-05) - Inadequate Emergency Team Pre-Fi re Planning:
The plant fire fighting operations are conducted by the fire brigade.
Each member of the brigade receives detail initial training with additional quarterly classroom training and quarterly drills provided.
Also, fire fighting strategies have been developed for all safety related areas of the plant. This item is closed.
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b.
(Closed) Inspector Followup Item (302/78-24-03) - Treatment of Wooden Materials With Fire Retardent: The licensee stated that all wood for.
scaffolding and temporary structures located in the plant is treated with a fire retardant chemical.as required by Procedure EM 101, Fire
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Protection Plan. Section 6.2.
Therefore, this item is closed.
c.
(0 pen) Inspector Followup Item (302/80-40-02) - Licensee's Inspection and Evaluation of Fire Damper Installation: On October 19-23, 1981 the licensee conducted an inspection of all fire damper installations and found a number of discrepancies.
Work request Nos. 28640, 28641, 28642, 28643, 28788, 28789 and 28790 have been issued to make the necessary repairs.
The principle discrepancies include improper mounting or attachment of the damper to the duct, inadequate sealing of area between duct and fire barrier and installation of electrical damper activators in such a manner as to possibily 'interfer with the automatic closure of the dampers. This item is to remain open pending completion of the required repairs and modifications.
d.
(Closed) Inspector Followup Item (302/80-40-03) - Fire Protection Administration Procedures Do Not Meet the NRC Guidelines: The licensee has developed fire fighting strategies for all hazardous and safety related areas of the plant but has not provided a procedure to imple-ment these fire fighting strategies. However, refer to paragraph 7.a below.
Procedure EM-101 has been revised to include "No Smoking" restrictions. The licensee has elected not to revise Procedure CP-118, Fire Prevention Work Permit Procedure, to extend the hazard from welding and cutting operations from a distance of 20-25 feet to 35 feet as listed in the NRC guidelines and NFPA criteria.
In view of.the licensee's fire watch training program and apparent good control over these hazards the procedures are considered to meet the intent of the NRC guidelines. This item is closed.
6.
Fire Protection Modifications a.
Reactor Building Standpipe System (MAR 79-11-11B): A fire hose stand-pipe system is being installed in the reactor building. This installa-tion was approximately 90% complete. The QC group is inspecting weld je4nts and the seismic hangers.
Test procedures were being prepared for hydrostatic and flushing tests of the system. The inspector toured the containment and noted that the design and installation of this system appears to meet the commitments of NRC by FPC's letter (File Code 3-03-a-3) of January 8,1979. Fire hose is not to be provided for the hose connections within containment.
However, hose is to be provided adjacent to the personnel entrance to the containment.
b.
Fire Detection System (MAR 80-09-04): A fire detection system is being installed _over the reactor coolant pumps, over some cable trays in the reactor building and in portions of the auxiliary and intermediate
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buildings.
The inspector conducted a walk through inspections of the installation and reviewed QC inspection report QCIR 81-107. It i
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appeared that the installation of this system will meet the commitments made to the NRC by FPC's letter of December 6,1979. QC inspections of the fire alarm and detection system installation is to include 10% of the conduit runs, one reactor coolant pump system installation and all of the installation for the cable trays inside the. reactor building.
Documentation of the cable pulls, wiring terminations, complete system installation inspection and detail functional tests are to be provided by the construction organization (Catalytic).
7.
Fire Protection / Prevention Administrative Procedures:
The licensee's fire protection / prevention procedures were previously reviewed by the inspector and as documented in Report No. 50-302/80-40 found to comply with the NRC guidelines except for the following three areas:
fire fighting strategies, smoking restrictions and welding, cutting and grinding operations. As noted in above paragraph 5.d the licensee has taken the appropriate action to correct these discrepancies. However, the licensee had not initiated a procedure to implement the administra-tion of the fire fighting strategies. The licensee committed during this inspection to develop an administrative procedure for these strategies to include a requirement for maintaining the document up to date, and identifying the distribution of the strategies. This item is identified as Inspection Followup Item (302/81-25-01), Implementation of an administrative procedure for the fire fighting strategies, and will be reviewed during a subsequent NRC inspection.
b.
Fire Brigade (1) Organization The plant fire brigade is composed of personnel from Operations, Chem Rad and Maintenance (Building Service) Departments.
The inspector reviewed the operations log for fire brigade assignments and fire brigade. roster and verified that at least five qualified fire brigade personnel and sufficient operations personnel were on duty to meet the provisions of the Technical Specification on the following dates:
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September 7,1981
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September 28, 1981 November 8, 1981
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November 18, 1981
(2) Training and Drills-The inspector reviewed the training records for six brigade members from the operations group and three brigade members from the Chem Rad group.
Each of these brigade members had received initial fire brigade training and quarterly training for the first
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three quarters of 1981. Also each of these members had partici-l pated in at least one brigade drill, were respirator qualified and had received a physical examination.
The training. met the requirements of licensee's procedure EM-101, Fire Protection Plan.
The inspector reviewed the drill. records for 1981 and noted that
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between January and October. a total of 18' drills had been.
conducted. The frequency of the drills also appeared to meet the requirements of EM-101.
(3) Fire Brigade Equipment A sufficient quanity of turnout gear (coats, boots, helmets,.etc.)
is provided to equip the fire brigade members. This equipment is stored in several areas in the plant. Additional equipment such as fire hose, nozzles, self contained breathing. apparatus, portable exhaust fans is stored on two carts located in. the auxiliary building and turbine building. This equipment appeared to be adequately maintained, Presently, the licensee has 26 self contained breathing apparatus and approximately 26 spare cylinders. The units are refilled on site by means of an air compressor. The number of units'available and the refilling capability were in'conformance with the commit-ments to the NRC.
c.
Inspection and Test of Fire Protection Systems'
(1) Documentation The inspector reviewed the following surveillance inspection and test records for the dates indicated:
(a) SP-190, Channel Functional and Circuitry Operability of Fire Detection Instrumentation (Monthly)
December 4,1980 through November 10, 1981 (b) SP-364, Fire Hose Station Inventory and Hydrant Operability Test (Monthly)
January 25, 1981 through October 24, 1981 (c)
SP-366, Fire System Annual Valve Surveillance (Annual)
April 10,1980 and April 12, 1981 (d) SP-607, Fire Damper Inspection (Annual)
October 22, 1980 and October 27, 1981
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The licensee's 1981 inspection noted a number of fire damper
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installation discrepancies. Work orders have been issued to correct these discrepancies.
Refer to above paragraph 5.c
for details.
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(e) SP-805, Surveillance of Fire Doors (Monthly)
January 14, 1981 through November 11, 1981 No discrepancies were noted other than those listed for the fire dampers.
(2) Test Evaluation On November 19, 1981 the inspector witness the licensee's test of the three fire pumps.
These pumps were satisfactorily tested using Procedure SP-363, Fire Protection System Tests.
d.
Plant Tour A tour of the plant was made by the inspector. This tour was made to review the fire protection modifications of the detection system and reactor building standpipe system and to review the general fire prevention features provided for the plant. As a whole, the licensee was adhering to the administrative - procedures for the control. of combustibles, flammable,'and combustible liquids and gases and open flame ignition sources.
Fire hydrant equipment hou:,e No. 2 was inspected and the required equipment was provided and properly stored.
However, the fire doors (Door A-202) between the hot machine shop and 119 foot elevation of the auxiliary building were found wedged-and blocked in the open position on January 17, 1981. These doors were not arranged to be automatically self closing and latching due to inopera-tive door closers and latching handware and a fire watch was not posted.
Technical Specification Section 3.7.12 requires all fire-barriers protecting safety related areas to be functional at all' times.
If the penetration fire barriers become non-functional a continuous fire watch is required to be established on at least one side of the affected penetration within'one hour.
The failure to provide a fire watch for the non-functional fire barrier is identified as Violation Item (302/81-25-02), Nonfunctional Fire Barrier Between Hot Machine.
Shop and Auxiliary Building.
A similar item involving one of the emergency diesel generator doors was previously identified by NRC Report 81-21.
With the areas examined, except as noted above, no additional viola-tions or deviations were identifed.