ML19305C565
| ML19305C565 | |
| Person / Time | |
|---|---|
| Site: | Hatch |
| Issue date: | 02/06/1980 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19305C561 | List: |
| References | |
| 50-321-80-02, 50-321-80-2, 50-366-80-02, 50-366-80-2, NUDOCS 8003310088 | |
| Download: ML19305C565 (5) | |
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O APPEhTIX A NOTICE OF DEVIATION Georgia Power Company License Nos. DPR-57 Hatch Nuclear Plant
& NPF-5 Based on the results of the U.S. Nuclear Regulatory Commission inspection conducted on January 8-11, 1980, certain of your activities appear to deviate from your com-mitments to the Commission.
The plant's fire protection plan and required modifications are described within the licensee's document entitled " Evaluation of the Hatch Nuclear Plant Fire Pro-tection Program" dated October 1976 with Amendment Nos. I through 7 (EFPP) and in NRC's Fire Protection Safety Evaluation Report (FPSER) for the facility dated October 4, 1978, which is Amendment No. 60 to Operating License No. DPR-57 and part of initial Operating License No. NPF-5.
The following items were found incomplete after the stated completion date or the modifications failed to meet the provisions of the applicable guides, codes or standards which were referenced by the EFPP:
A.
Section IV.B.7 of the EFPP states in part that the ten Quality Assurance (QA) criteria of Section C of Appendix A to NRC's Branch Technical Position APCSB.9.5-1 (BTP 9.5-1) will be applied commensurate with the controls described in the Operatfor.al QA Program and that the QA program for fire
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protection will be under the management control of the QA organization.
Contrary to the above, documentation is not available or is not easily retrievable to demonstrate that the fire protection modifications required by the FPSER and the EFPP were accomplished under the following ten QA program criteria as listed in BTP 9.5-1:
(1) Design control and procedure control (2) Instructions, procedures, and drawings (3) Control of purchase materials, equipment and services (4) Inspection (5) Test and test control (6) Inspection, test and operating status Functional tests were, however, conducted and recorded on the fire detection systems.
(7) Non-conforming items (8) Corrective action (9) Records (10) Audits.
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Georgia Power Company Appendix A Hatch Nuclear Power Plant Notice of Deviation B.
Section IV.C.3.c of the EFPP states in part that all of the automatic sprinkler systems installed at the plant conform to the requirements of National Fire Protection Association Standard No. 13 (NFPA-13), Sprinkler Systems.
Contrary to the above, the sprinkler system installations do not fully meet the requirements of NFPA-13. Examples are as follows:
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(1) The sprinkler piping for pre-action systems which contain over 20 heads are not supervised as required by Section 5-3.5.2 of NFPA-13.
(2) The sprinker deflectors in many areas are located up to twice the distance beneath ceiling / roof structures than that permitted by
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Section 4-3 of NFPA-13.
9 (3) Serious obstruction to discharge of water spray from the systems in some areas is provided from ventilation ducts, electrical cable trays, conduit, piping and building structural supports. This problem is most acute in the cable spreading room.
Sections 4-4.13 and B-4-2.3 of NFPA-13 require that additional sprinkler protection be provided in areas where obstructions are located.
(4) Closed type no ;1es for water spray type sprinkler systems located long distance beneath ceilings or roofs are not provided with heat collectors to assure prompt actuation of the nozzles in the event of fire as required by Section 3-16.8 of NFPA-13.
(5) Test pipes (main drains) arranged to properly test the water supply to each system are not provided as required by Section 2-9 of NPFA-13.
(6) The shut-off v-Ives to the water flow alarms on wet pipe systems are located the di charge side of the retarding chamber in lieu of the supply side as required by Section 3-17.4.3 of NFPA-13.
(7) Valves to the water flow alarm devices to the sprinkler syst ems are not of the type which can be scaled or locked an position as required by Section 3-17.4.5 of NFPA-13.
(8) The bolts for the flange fitting in the supply piping to the sprinkler /
standpipe system at the intake structure are too short nd do not meet the provisions of Section 3-13.1 of NFPA-13. This sitsstion may also exist on flange type fittings located in other areas.
C.
Section III.C.4.(b) of the EFPP states in part that the storage of transient l
combustibles within the east cableway of Unit I will be controlled by admin-l istrative procedures and by signs.
Contrary to the above, approximately 45 boxes of HEPA filters were stored within the Unit I cast cableway during this inspections. This storage was l
located adjacent to a sign which read: " CAUTION - Storage of Combustibies Prohibited".
Georgia Powc; Company Appendix A flatch Nuclear Power Plant Notice of Deviation D.
Section III.A of the EFPP states in part that fire prevention at the plant will be accomplished by early identification of and elimination of fire hazards through periodic inspections of areas to identify combustible materials or other fire hazards which may develop in these areas.Section III.B of the EFPP states in part that. housekeeping requirements are fulfilled by the building and grounds supervisor and foreman using good established housekeeping practices with housekeeping audited by periodic management inspections.Section III.C.4 of the EFPP states in part that a curb will be added around each pump division to control any oil that may leak from the pumps.
Contrary to the above, on January 9,1980, the curb area for the Unit 2 RilR pumps was found approximately 25% full of a water-oil solution which consti-tuted a fire hazard.
E.
Section III.C.4 of the EFPP states in part that the storage of transient combustibles within the river intake structure will be controlled by appropriately marking the floor areas.
Contrary to the above, the floor areas are not marked and/or signs are not provided to prohibit the storage of combustibles within the river intake structure.
F.
Section IV.C.2.a of the EFPP states in part that the exterior (fiie protec-tion) underground yard main loop is designed in accordance with NFPA-24, Outside Protection.
Contrary to the above, the supply connection from the exterior fire protec-tion water system to the sprinkler / standpipe system within the river intake structure is not provided with an independent outside control valve as required by Section 3-3.1 of NFPA-24. The existing control valve for the water supply to the building also controls the water to the fire hydrant installed adjacent to the intake structure.
G.
Section III.C.1.2 of the EFPP states in part that all openings in the fire walls or barriers around the control room will be provided with three-hour fire doors and that the wall between the control room and peripheral rooms will have a one-hour fire rating.Section IV.B.I.j states in part that all openings in fire rated walls will be protected by fire doors, frames and hardware that are listed by Underwriters Laboratories (UL). UL requires all fire doors to be installed in accordance with the provisions of NFPA-80, Fire Doors and Windows in order for the doors to retain their UL listing.
Contrary to the above, the fire doors in the fire walls / barriers between the control room and adjacent areas do not fully meet the provisions of NFPA-80 due to tha following:
(1) The fire doors between the control room and peripheral rooms (toilet and kitchen / administration area) are not provided with door closers as l
required by Section 2-8.4 of KFPA-80.
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Georgia Power Company Appendix A Hatch Nuclear Power Plant Notice of Deviation (2) The fire / security doors between the control room and turbine buildings are not provided with positive type latching devices as required by Section 2-8.2 of hTPA-80.
H.
Section III.C.I.1 of the EFPP states in part that smoke detectors will be installed within the peripheral rooms adjacent to the control room.
Contrary to the above, rate of rise type (heat) fire detectors have been installed in the peripheral room kitchen in lieu of smoke detectors.
I.
Section IV.C.I.4.(g) of the EFPP states in part that the automatic sprinkler system install.ed in the 130-foot control building corridor will be designed such that it will not spray on the safety related cabinets that are located in the corridor.
o.
l Contrary to the above, four safety related cabinets are located in the corridor directly beneath the ceiling level sprinkler system. Protection has not been provided to prevent the sprinkler system from discharging water directly on to these cabinets, nor has an evaluation been made to determine if the inherent protection provided by the construction of the cabinets is adequate to prevent water damage to this equipment.
J.
Table 3 Item No. III.39 (Response No. 25(a) to NRC questions of June 13, 1977) of the EFPP states that a mobile platform for fire fighting operations will be provided in both the northwest and southwest cable areas of each unit.
Contrary to the above, a mobile platform was not located in the northwest cable area of unit 1.
K.
Table 3 Item No. III.43 (Response to NRC question 25.e. (3) of June 13,1977) states in part that the control valves in the drain piping system from the Unit I and 2 reactor recirculation M-G set rooms which terminate at the floor of the 130-foot elevation of the reactor building will be maintained closed with the valves locked in the closed position.
Contrary to the above, the control valves in the drain piping from the reactor recirculation M-G set rooms were found closed but were not locked in the closed position.
L.
Section IV.C.2.c of the EFPP states in part that a floor to ceiling fire barrier will be provided between each fire pump.
Contrary to the above, a fire barrier has been provided between each pump but the fire pump controller and battery charger for diesel engine fire pump No. 2 are located within the enclosure for fire pump No. 3.
A fire involving pump No. 3 could place pump No. 2 out of service.
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Georgia Power Company Appendix A Hatch Nuclear Power Plant Notice of Deviation M.
Section IV.C.3.b of the EFPP states in part that all interior fire protection control valves to the sprinkler systems for Unit 1 are designed to give a local alarm if moved to the wrong position and the control valves for the Unit 2 systems are designed to sound an alarm in the main control room if moved to the wrong position. Furthermore, all control valves for the Unit I systems will be maintained locked in the proper position by a key control procedure.
Contrary to the above, the following discrepancies were noted:
(1) The following Unit I sprinkler system control valves were found open but not locked in the open position as required:
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(a) Cable Spreading Room (b) IIVAC Area - 158 Foot Elevation (c) RPS Area (2) The following Unit 2 sprinkler system control valves were found open but are not designed to sound an alarm in the main control room if moved to the wrong position:
l (a) Cable Spreading Room (b) Control Room Building - 130 Foot Corridor (c) RPS Area N.
Section IV.B.4.h of the EFPP states in part that the air compressor for refilling the self-contained breathing apparatus which are provided for use in the event of fire or other emergencies will be located within a special receptacle in the diesel generator building and will be arranged for manual i
connection to an active power supply in the event of loss of offsite power.
Contrary to the above, the air compressor has been installed within the water j
treatment building in which a power source is not readily available in the event of loss of offsite power.
The above deviations are applicable for both units, except Items C., J., and L.,
are applicable to Unit I and Item D is only applicable to Unit 2.
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