IR 05000424/1986013
| ML20205M911 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 04/03/1986 |
| From: | Conlon T, Wiseman G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20205M910 | List: |
| References | |
| 50-424-86-13, 50-425-86-07, 50-425-86-7, IEIN-84-92, NUDOCS 8604150593 | |
| Download: ML20205M911 (8) | |
Text
{{#Wiki_filter:ma ner UNITED STATES ' /'
NUCLEAR REGULATORY COMMISSION [ 'n REGION 88 g j 101 MARIETTA STREET.N.W.
ATLANTA. GEORGI A 30323 \\...../
Report Nos.: 50-424/86-13 and 50-425/86-07 i Licensee: Georgia Power Company j P. O. Box 4545 Atlanta, GA 30302
Docket Nos.: 50-424 and 50-425 License Nos.: CPPR-108 and CPPR-109 Facility Name: Vogtle 1 and 2 Inspection Conducted: February 24-28, 1986 Inspector: k- [/ tuhrt S[[b G. R. Wiseman~ Date Signed Approved by EW F Y @ ~.fd-T. E. Conlon, Section Chief Date Signed Engineering Branch Division of Reactor Safety SUMMARY ' Scope: This routine, unannounced inspection entailed 38 inspector-nours on site in the areas of fire protection / prevention.
Results: No violations or deviations were identified.
i 8604150593 860407 PDR ADOCK 05000424 PDR t O - - - .,- ,. -. - . - .,. ,.
- _.. .,. _.
REPORT DETAILS 1.
Persons Contacted , Licensee Employees
- R. E. Conway, Senior Vice President M. S. Dean, Senior Mechanical Engineer, Construction J. O. Dorough, Manager, Administrative Operations
- M. H. Googe, Project Construction Manager
- G. A. McCarley, Project Compliance Coordinator D. McCary, Civil / Heating, Ventilating, and Air Conditioning (HVAC)
Supervisor j
- W. E. Mundy, Construction Quality Assurance Supervisor
- R. A. Sprankle, Senior Engineer (Fire Protection)
, '
- H. Varnadoe, Plant Engineering Supervisor, Nuclear Operations
' Other Organizations j R. L. George, Project Engineering Manager, Southern Company Services H. W. Holcombe, QA Manager, Pullman /Kenith-Fortson, (P/KF) l A. Strunk, Senior Engineer, Bechtel i J. Werner, Q6 Manager, Automatic Sprinkler Corporation NRC Resident Inspector
- J.
Rogge
- Attended exit interview
2.
Exit Interview The inspection scope and findings were summarized on February 28, 1986, with , I those persons indicated in paragraph above.
The inspector described the areas inspected and discussed in detail the inspection findings listed below. No dissenting comments were received from the licensee.
a.
Inspector Followup Item (424/86-13-01 and 425/86-07-01), Implementation
of Fire Protection System Valve Alignment and Control Verification , ' i Procedures paragraph 5.a.
b.
Inspector Followup Item (424/86-13-02 and 425/86-07-02), Fire Main-Yard Piping Discrepancies from the Guidelines of NFPA 24 paragraph 5.b.
c.
Inspector Followup Item (424/86-13-03 and 425/86-07-03), Engineering , Analysis, Testing, and Justification for Non-Standard Penetration Seal Configurations paragraph 5.e.
... .,, -,,. ,,,m-__ __ ..,,y_- ,.,,. ,.. -,, . -m_ , ,. _,-- ,. -
.
, d.
Inspector Followup Item (424/86-13-04 and 425/86-07-04), Implementation of Permanent Plant Fire Prevention / Protection Program During Area Turneycrs paragraph 5.f.
,
The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspection.
3.
Licensee Action on Previous Enforcement Matters (0 pen) Unresolved Item (424, 425/84-34-04), Apparent Substandard Fire a.
, Damper Installation: The licensee has recently performed fire tests on the plant fire damper and associated penetration seal configurations.
The tests results are presently under review by Underwriter's Laboratory for their approval.
The licensee stated that the test ] program will be submitted to NRC/NRR for review and approval. Pending this review this item remains open.
b.
(Closed) Unresolved Item (424, 425/84-34-05), Apparent Fire Damper QA Inspection and Documentation Discrepancies: The inspector reviewed the Pullman /Kenith-Fortson (the licensee's HVAC contractor) fire damper inspection procedure JP-14.2, Revision 2C.
This procedure requires i inspection of the fire damper installation for proper: (1) damper identification (2) damper location (3) air flow direction (4) damper condition (damaged or missing parts) (5) damper cycle operation (drop test) Based on this review the licensee's fire damper inspection program appears adequate.
l 4.
Unresolved Items Unresolved items were not identified during the inspection.
5.
Permanent Plant Fire Protection Features a.' Fire Pumps (Module 640538) Three 1001, capacity fire pumps are designed to provide fire protection
water for the plant. Two pumps are diesel driven and located in one pump house.
The third pump is electric driven and is located in a-i separate pump house. The fire protection water supply i s ' f rom two
300,000 gallon fire water storage tanks located onsite. At the time of the inspection one of the diesel driven pumps (Pump C-2301-P4-003) was out-of-service due to an engine overhaul and replacement of the flywheel. The iristallation of the power supply and header piping to !
< _ _ _ _ _ _ - -. , _ _ _ _ _._ __ _ ___ ~_, ,- _,- __ _.. _ _ _ _. . . _. _..
._ > -_ _ . _. _ ._.
. . _
. !
l . i the electric pump (Pump C-2301-P4-002) is not yet complete. The other diesel pump (Pump C-2301-P4-005) has been turned over to. Nuclear Operations and was in service.
A review of the pump suction and i discharge piping and valves revealed that the fire water system valves were properly aligned, however no provision for locking and securing
} valve HV-7943 in its proper aligned (open) position had been taken.
Should this valve be inadvertently closed, fire pump suction to the , i plant fire water supply could be lost. Nuclear Operations has not yet
developed permanent plant procedures for verification of fire
protection system valve control and alignment. This is identified as
Inspector Followup Item (424/86-13-01 and 425/86-07-01),' Implementation of Fire. Protection System Valve Alignment and Control Verification Procedures.
, IE Informac.>on Notice No. 84-92 , l IE Information Notice 84-92, Cracking of Flywheels on Cummins Fire Pump i j Diesel Engines, was issued on December 17, 1984. This Notice alerted j licensees of a potential problem of cracking flywheels on certain j
models of Cummins diesel engine driven fire pumps. The licensee stated
that during overhaul, the flywheel of pump C-2301-P4-003 was inspected i and at least six crack indications were found. The licensee documented this action by issuance of Deficiency Report (DR) T-86-533 on February 17, 1986.
The defective flywheel was replaced with a new
flywhee] Part No.
(3047462) per the engine manufacturer's , ! recommendations.
The flywheel of diesel driven fire pump C-2301-P4-005 has not yet been
inspected. This will be reviewed during a subsequent NRC inspection.
, ! b.
Exterior Yard Fire Protection Piping System (Module 640538) i i The underground fire protection piping throughout the yard areas is
cement mortar-lined ductile-iron type.
The inspector reviewed the
installation of portions of the underground loop in the area of the ' switchyard and the water mains to the diesel generator building / aux - iliary feedwater pump areas. The inspector noted that the loop design i at piping elbows, bends, and hydrant tees does not include installation i of thrust blocks or anchor designs similar to those provided in
NFPA 24, Section 8-6.2 - Methods of Anchoring Fire Mains and Figures j A-8-6.2 of this section. Additionally, it appeared that a portion of i the pipe supports for the diesel building and auxiliary feedwater pump i area fire system yard piping were not anchored. These discrepancies
are identified as Inspector Followup Item (424/86-13-02 and 425/86-07-02), Fire Main-Yard Piping Discrepancies from the Guidelines ' of NFPA 24, and will be reviewed during a subsequent NRC inspection.
! -
i j
i ! ... _... _., _ -, _ ~ _ _.. _ _ _. _. _,.. -,, _,. _.,. _ _,, .. _...,, _.. _ _ - -., _ _. _ _ _,.
i i
The yard fire main system has not been declared fully operational pending flushing and preoperational testing. Portions of the system and its components are provided surveillance and maintenance i instructions through the Nuclear Operations Temporary Fire Protection Procedures TFPP-400 thru TFPP-437C.
The following Nuclear Operations Temporary Fire Protection Procedures were reviewed: Procedure No.
Revision No.
Procedure Title , l TFPP-403-C
Fire Hydrants Monthly Visual Inspection TFPP-411-C
Fire Suppression System - Quarterly oIV Cycle TFPP-413-C
Fire Pumps Starting Batteries Quarterly Specific Gravity Test TFPP-420-C
Fire Hydrants - Semiannual Barrel Inspection and Lubrication . TFPP-433-C
Fire Hydrants Annual Operational Test l TFPP-437-C
Fire Suppression System - I Annual Operational Test The inspector pointed out to the plant Nuclear Operations fire protection staff, several minor discrepancies and corrections to these procedures.
These are to be incorporated into the development of permanent plant procedures. Overall these procedures, for the items covered, provide sufficient guidance to assure that surveillance and maintenance is provided.
The inspector reviewed the Nuclear Operations Maintenance Records, as noted below, and verified that the surveillance and maintenance for certain fire protection features were being accomplished: Date Required PM of Last Equipment Procedure No.
Frequency Inspection Post Indicator TFPP-411-C Quarterly 11/08/85 Valves (PIV's) Fire Hydrants TFPP-403-C Monthly 12/02/85 ] ___ _ -. .- -.- .- - - _ - - , .- - ._.
- -_-. -.
, The inspector also performed a physical walkdown of the equipment inventory of fire hydrant hose houses 588 and 610.
Except for the shortage of two flashlights, the designated hydrant hose' house inventories appeared complete.
The existing equipment appeared to be properly maintained and stored in a ready condition.
c.
Automatic Sprinkler Systems Installation of the sprinkler systems throughout the safety related structures is in progress.
For those systems of which the mechanical portions have been completed, the following inspection and test, record data was reviewed to verify that the systems were installed under the QA/QC program to ensure that the systems are installed in accordance with the design and construction documents.
Inspection Hydrostatic Test No.
Location Test Date 96-029-1-1 Diesel Generator Building 08/14/85 and Electrical Tunnel (IT4A) 91-030-5-1 Electrical Tunnel (1T4B) 07/03/85 88-031-3-1 Diesel Generator Building - 06/07/85 Train B (System 031) . 89-032-1-1 Diesel Generator _ Building - 07/02/85 Train A (System 032) These tests appeared to meet the 200 psi test pressure for two hours duration testing requirements of NFPA-13, Sprinkler Systems, and are satisfactory.
A tour was made of the diesel generator building to. review the installation of the automatic sprinkler systems. The sprinkler systems for the diesel generator areas (systems 031 and 032) are designed as pre-action type systems, but are presently being maintained as wet pipe systems pending completion of the fire detection system installation and system pre-operational functional tests.
This results in the pre-action valve installations being slightly modified to allow the system to function as a wet pipe system. These valves will be reviewed during a subsequent NRC inspection to verify ' conformance 'to the manufactures design and installation requirements.
d.
Fire Dampers An inspection was made of the following fire dampers to verify that the appropriate QA inspection records were provided as designated in Pullman /Kenith-Fortson fire dampers inspection procedure JP-14.2.
No discrepancies were noted.
a
-_ _
i ' Final PKF QA/QC Damper No.
Location Inspection Date A-1531-S7-510 Control Room 12/17/84 A-1531-S7-513 Control Room 12/10/84 A-1531-S7-514 Control Room 11/16/84 1-1551-57-627S Aux. Bldg. Level 2 06/07/84
A-1533-S7-678 Spreading Room 01/08/86 ^ , 1-1561-S7-214 Control Bldg. Level C 12/02/84 e.
Fire Barrier Penetration Seals l A visual inspection was made of fire barrier penetrations in the
Control Building areas. Installation of fire barrier penetration seals within those areas are in process.
In general, it appeared that ' several of the installed penetration seal configurations do not conform to previously tested and approved designs in that: Many cable tray penetration block-out openings appear to be larger - i
than the maximum size wall openings designated by approved configurations tested by Underwriter's Laboratory Standard, UL ' 1479, Through-Penetration Firestops.
l Fire barrier seals are not designated for the high voltage - bus-duct openings which penetrate the switchgear room fire area boundaries.
- Cable tray supports are installed within fire barrier penetratien , openings which may allow heat transfer through the barrier seal.
The joint seals in the seismic gap of fire barriers separating the - ' Control and Turbine Buildings and the Containment and Auxiliary , Buildings appear to contain combustible styrofoam and do not
appear to afford three-hour fire resistance protection.
These issues are to be further evaluated by the licensee and is identified as Inspector Followup Item (424/86-13-03 and 425/86-07-03), Engineering Analysis, Testing, and Justification for Non-Standard Penetration Seal Configurations.
Review of this item and the final QA/QC inspection documentation for penetration fire stops will be conducted during a future NRC inspection, f.
Plant Tours i The inspector made tours of the plant to verify that the licensee was implementing a fire protection and prevention program relative for the construction activities on the site.
These tours included walk throughs of portions of the Control Building, Auxiliary Building, Fuel Handling area, Diesel Generator Building, Switchyard, and yard
-- - - - - -
_ .t
structures including the fire pump houses. Construction activities are nearing completion for some safety-related structures which have been designated for turnover to Nuclear Operations in the near future.
Permanent plant fire protection / prevention procedures have not been , issued for these areas.
In the interim, the plant fire protection
program will be implemented through the Nuclear Operations Department Standing Order, entitled Temporary Fire Protection Operational Guidelines issued, January 30, 1986. These guidelines however, do not address a fire prevention program related to housekeeping and control ' of combustibles and ignition sources in areas designated for turnover to the plant operations and startup organizations. This is identified as Inspector Followup Item (424/86-13-04 and 425/86-07-02), Implemen-tation of Permanent Plant Fire Prevention / Protection Program During Area Turnovers, end will be reviewed during a subsequent NRC inspection.
Within the areas examined, no violations or deviations were identified.
6.
Inspector Followup Items (IFI)
(0 pen) IFI (424, 425/84-34-01), Removal of All Combustible Scaffolding, Planking, and Temporary Construction Structures Required Prior to Licensing: By letter dated January 10, 1985, (File No. X7BA01-C5, Correspondence No. S-1635) from the Vogtle Project Construction Manager to all site contractors, the licensee directed that all combustibles involved in construction activities would be removed from an area prior to its area turnover. This is to be completed for Unit I areas prior to September 1, 1986.
This item remains open pending implementation during Unit 1 area turnovers.
(0 pen) IFI (424, 425/84-32-02), Fire Pump Installation Discrepancies: This item remains open pending NRC review of the licensee's point-by point comparison of the fire pump switchgear to the requirements of NFPA-20 and completion of ongoing fire pump modifications.
(Closed) IFI (424, 425/84-34-03), Two Hour Rated Cabinet Not Provided For Storage of Automatic Sprinkler System Fire Protection Records: The licensee has provided two Underwriters Laboratory (UL) listed fire rated cabinets for storage of automatic sprinkler system fire protection records.
The inspector examined the file cabinets provided and they appear acceptable.
! - - - - - - - - - - - - }}