ML20141E889
ML20141E889 | |
Person / Time | |
---|---|
Site: | Cooper |
Issue date: | 04/10/1986 |
From: | Muller D Office of Nuclear Reactor Regulation |
To: | |
Shared Package | |
ML20141E880 | List: |
References | |
TAC-57951, NUDOCS 8604220415 | |
Download: ML20141E889 (10) | |
Text
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, / I'og UNITED STATES e NUCLEAR REGULATORY COMMISSION 7; ;p. WASHINGTON, D. C. 20555
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NEBRASKA PUBLIC POWER DISTRICT DOCKET NO. 50-298 COOPER NUCLEAR STATION AMENDMENT TO FACILITY OPERATING LICENSE
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Amendment No. 98 License No. DPR-46
- 1. The Nuclear Regulatory Comission (the Comission) has found that:
A. The application for amendment by Nebraska Public Power District dated May 31, 1985, as supplemented by submittal dated August 21, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B. The. facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the licensee is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license amendment and paragraph 2.C(2) of Facility Operating License No. DPR-46 is hereby amended to read as follows:
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(2) Technical Specification The Technical Specifications contained in Appendices A and B, as revised through Amendment No. , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
,%,- f er Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: April 10,1986 U-
ATTACHMENT TO LICENSE AMENDMENT NO. 98 FACILITY OPERATING LICENSE NO. DPR-46 DOCKET NO. 50-298 1.- Replace the following pages of the Appendix A Technical Specificattons with the enclosed pages. The revised areas are indicated by marginal lines.
Pages iii 216f 216g 216j 216k 216m
- 2. Add the following new page.
216k1 i
- TABLE OF CONTENTS (Cont'd.)
Page No.
SURVEILLANCE LIMITING CONDITIONS FOR OPERATION REQUIREMENTS 3.12 ADDITIONAL SAFETY RELATED PLANT CAPABILITIES 4.12 215 - 215f A. Main Control Room Ventilation A 215 B. Reactor Building Closed Cooling Water System B -
215b C. Service Water System C 215c D. Battery Room Vent D 215e 3.13 RIVER LEVEL 4.13 216 3.14 FIRE DETECTION SYSTDt 4.14 216b 3.15 FIRE SUPPRESSION WATER SYSTDi 4.15 216b 3.16 SPRAY AND/OR SPRINKLER SYSTEM (FIRE PROTECTION) 4.16 216e 3.17 CARBON DIOXIDE AND HALON SYSTEMS 4.17 216f l 3.18 FIRE HOSE STATIONS 4.18 216g 3.19 FIRE BARRIER PENETRATION FIRE SEALS 4.19 216h 3.20 YARD FIRE HYDRANT AND HYDRANT HOSE HOUSE 4.20 2161 3.21 ENVIRONMENTAL / RADIOLOGICAL EFFLUENTS 4.21 216n 4.22 216u 3.22 SPECIAL TESTS / EXCEPTIONS 216u A. Shutdown Margin Demonstration 216v
- 3. Training Startup 216w C. Physics Tests 216x D. Startup Test Program ;
i 5.0 MAJOR DESIGN FEATURES 5.1 Site Features 217 5.2 Reactor 217 5.3 Reactor Vessel 217 5.4 Containment 217 5.5 Fuel Storage 218 5.6 Seismic Design 218 5.7 Barge Traffic 218 Amendment No. 89, 97
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LIMITING CONDITIONS FOR OPERATION StiRUEILLANCE REQUIREMENTS
. 3.16 (cont'd) 4.16 (cont'd)
SPECIFICATIONS SPECIFICATIONS A. The Automatic Sprinkler Systems pro- A. The Automatic Sprinkler Systems pro-tecting the Cable Spreading Room, tecting the Cable Spreading Room, Cable Expansion Room, and Northeast Cable Expansion Room, and Ncrtheast Corner - 903 Ft. Elev. of Reactor Corner - 903 Ft. Elev. of Reactor Building shall be operable. Building shall be demonstarted to B. If the requirement of 3.16.A cannot be operable by:
be met, establish a continuous fire 1. At least once per 12 months by watch with backup fire suppression cycling each testable valve in equipment for the unprotected area the flow path through at least within I hour; restore the system one complete cycle of full to OPERABLE status within 1/* days travel, or prepare and submit a Special Report to the Commission within. 2. At least once per 18 months:
the next 30 days outlining the a) By performing a system action taken, the cause of the functional test which inoperability and the plans and includes simulated schedule for restoring the system automatic actuation of to OPERABLE status. the system, and 3.17 CARBON DIOXIDE AND HALON SYSTEMS 1) Verifying that the automatic valves in APPLICABILIT' the flow path actu-Applies to the operational status of the ate to their correct High Pressure Carbon Dioxide Extinguishing po *. ions on a test System protecting the Diesel Generator signal, and Rooms and the Halon Suppression System 2) Cycling each valve in protecting the Service Water Pump Room. e s OB.TECTIVE plant operation To assure continuous Automatic Fire Pro- through at least one tection for the Diesel Generator Rooms C P** I
- l and the Service Water Pump Room.
b) By in etion f the spray SPECIFICATIONS headers to verify their A. The High Pressure Carbon Dioxide I"*'E#IE7' Extinguishing System protecting 4.17 CARBON DIOXIDE AND HALON SYSTEMS the Diesel Generator Rooms shall l be operable. APPLICABILITY B. The Halen 1301 Fire Suppression Applies to the operational status of the System protecting the Service High Pressure Carbon Dioxide Extinguishing Water Pump Room shall be operable System Protecting the Diesel Generator with at least one storage tank Rooms and the Halon Suppression System charged to at least 95% of the Protecting the Service Water Pump Room. I design quantity (650 lbs) and SPECIFICATIONS 90% of full charge pressure.
Extinguishing System protecting j the Diesel Generator Rooms shall j be demonstrated operable by:
- 1. At least once per 6 months, the High Pressure Carbon Dioxide storage cylinders should be weighed.
Amendment flo. 42, 66, 86 -216f-1
, ' LIMITING CONDITIONS FOR OPERATION 3.17 (cont'd)
SI'RVEILLANCE REQUIREMEWTS 4.17 (cont'd) f C.- If the requirement of 3.17.A and 2. At least once per.18 months by 3.17.B cannot be met: verifying the system valves,
- 1. Establish a continuous. fire "I'#"*' ** "" "I*** **"" -
watch with backup fire suppres- I'*I " " ""# I"E*'1 * * "" ~
sion equipment for the unprotected dampers actuate to a simulated area (s) within 1 hourt restore the aut natic and manual actuation system to OPERABLE status within 14 days or prepare and submit a
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- Special Report to the Commission verify fl v fr a each nozzle.
within the next 30 days outlining B. The Halon 1301 Fire Suppression Sys-the action taken, the cause of the tem protecting the Service Water inoperability and the plans and Pump Room shall be demonstrated schedule for restoring the operable:
system to OPERABLE status.
- 1. At least once per six months by 3.18 FIRE HOSE STATIONS recording the quantity.of Halon APPLICABILITY and the pressure of each Halon storage tank. . I Applies to the operational status of the Fire Hose Stations in the Control and 2. At least once per 18 months by Reactor Buildings, verifying the system valves, alarms, and associated venti-OBJECTIVE 1ation motor interlocks and To assure continuous manual fire fighting dampers, actuate to a simulated capability provided by existing Fire Hose aut natic and manual actuation Stations. signal and by performing an in-spection-to assure the nozzles SPECIFICATIONS are unobstructed.
A. The Fire Hose Stations shown in 4.18 FIRE HOSE STATIONS Table 3.18 shall be operable.
APPLICABILITY B. If the requirement of 3.18.A cannot be met, route an additional hose t Applies to the operational status of the the area protected by the inoperable Fire Hose Stations in the Control and Fire Hose Station from an operable Reactor Buildings.
Fire Hose Station of equivalent SPECIFICATIONS capacity within I hour. '
A. The Fire Hose Stations in the Control Building and Reactor Building shall be demonstrated to be operable by:
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- 1. At least once per 31 days by:
a) Visual inspection to assure all required equipment is 1 at the station.
- 2. At least once per 18 months by:
a) Removing the hose for-in-spection and re-racking, and l b) Replacement of all degraded l gaskets in couplings. )
- 3. At least once per 3 years by:
a) Partially opening each hose station valve to verify valve OPERABILITY and no Amendment No. 42, 86 -216g- flow blockage, and s
.h
. TAELE 3.14
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FIRE DETECTION INSTRUME:iIS INSTRUMENT ID NO.
1 Reactor Building l.
859 & 881 Elev. FD-TD-18-2 (Covers RCIC, FP-TD-18-3 Core Spray, RHR, and FP-TD-19-2 HPCI Pumps) FP-TD-19-3 FP-TD-20-2 FP-TD-20-3 FP-TD-20-4 FP-TD-20-5 FP-TD-21-2 FP-ID-21-3 903 Elev. FP-SD-18-1 FP-TD-18-4 FP-SD-19-1 FP-SD-20-1 FP-SD-21-1 931 Elev. FP-SD-23-1 FP-SD-23-2 l FP-SD-23-3 FP-SD-23-4
[
958 Elev. FP-SD-24-1 FP-SD-24-2 l
FF-SD-24-3
! FP-SD-24-4 i FP-SD-24-5 FP-SD-24-6 976 Elev. FP-SD-26-1 Covers Standby FP-SD-26-2 Liquid Control Pump and FP-SD-25-1 l Standby Gas Treatment FP-SD-25-2 FP-SD-25-3 FP-SD-25-4 r FP-TD-25-5 l 1001 Elev. FP-TD-26-3 Also Fuel FP-TD-26-4 Storage Area FP-TD-25-6 i FP-TD-25-7 l
f Legend FP = Fire Protection H = Halon 1301 l TD = Thermal Detector CO2 = Carbon Dioxide l DG = Diesel Generator FD = Flame Detector SD = Smoke Detector 1st Digit Instr. ID No. = Zone 2nd Digit Instr. ID No. = Instr. No.
-216j-Amendment No. 42, 66
7.
- IXSTRCin;T 1.0 CATION U;STRI!ME;T ID 80.
-2 Control Roem FP-SD-17-1 FP-SD-17-2 FP-SD-17-3
- 3. Cable Snreadine Room FP-SD-16-1 FP-SD-16-2 FP-SD-10-3 FP-SD-16-4 FP-SD-16-5 FP-SD-16-6.
Cable Expansion Reem FP-SD-16-7 FP-SD-16-8 4 Switchgear Rooms DC Switchgear Eoces FP-SD-15-2 FP-SD-15-3 Critical Switchgear Room FP-SD-22-1 FP-SD-22-2 5 ' Station Battery Rooms FP-SD-15-1 FP-SD-15-4 FP-SD-15-1A FP-SD-15-4A 6 Diesel Generator Rooms FP-SD-10-l' FP-SD-10-2 FP-SD-10-3 FP-SD-10-4 CO2-SD-DC-1A CO2-SD-DG-1B CO2-SD-DG-1C CO2-SD-DG-1D CO2-SD-DG-2A CO2-SD-DG-2B CO2-SD-DG-2C CO2-ED-DG-2D l
7 Diesel Fuel Storage Rooms CO2-TD-DG-1A CO2-TD-DG-1B l
I l
Amendment No. 82, 90 -216k-l
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l
.- INS!ELYENT I.CCATICN INSTRLHENT ID NO.
8' Safetv-Related Ecuipment not in Reactor Building l- RHR Service Water Booster Pumps FP-SD-14-3 i-Emergency Condensate Storage Tanks FP-SD-14-1 Service Water Pumps FP-SD-32-1
.FP-SD-32-2 FP-SD-32-3 FP-SD-32-4 FP-FD-32-5 FP-FD-32-6 HSW-SD-H1 HSW-SD-H2 HSW-SD-H3 l HSW-SD-H4 i 'HSW-SD-H5 HSW-SD-H6 HSW-TD-H11 HSW-TD-H12 HSW-TD-H13
- HSW-TD-H14
- HSW-TD-HIS HSW-TD-H16 9 Auxiliary Relav Room & Reactor Protection System Rooms Auxiliary Relay Room FP-SD-15-9 Reactor Protection System Room 1A FP-SD-15-7
- Reactor Protection System Room 1B FP-SD-15-8 i
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, 3.14-3.19/4.14-4.19 BASES 3.14/4.14 FIRE DETECTION INSTRUMENTATION OPERABILITY of the -fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires. This cap-ability.is required in order to detect and locate fires in their early stages.
Prompt detection of fires will reduce the potential for damage to safety related equipment and is an integral element in the overall facility fire protection program.
In the event that a portion of the fire detection. instrumentation is in-operable, the establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is returned to service.
3.15-3.18/4.15-4.18 FIRE SUPPRESSION SYSTEMS THE OPERABILITY of the fire suppression systems e.nsures that adequate fire suppression capability is available to confine and extinguish fires occurring in any portion of the facility where safety related equipment is located. The fire suppression system consists of the water system, spray and/or sprinklers, CO '
2 Halon 1301, and fire hose stations. The collective capability of the fire l suppression systems is adequate to minimize potential damage to safety related equipment and is a major element in the facility fire protection program. The Halon Fire Suppression System consists of two storage tanks, each exceeding the design capacity required for extinguishment of a fire in the service water pump room in accordance with the National F.re Codes. Each tank, containing 650 lbs.
of Halon 1301, can flood the Service Water Pump Room to a uniform concentration of 8 percent, exceeding the 3.5 percent level s>.'ficient to extinguish a flame in the region.
In the event that portions of the fire suppression systems are inoperable, alternate backup fire fighting equipment is required to be made available in the affected areas-until the affected equipment can be restored to service.
In the event the fire suppression water system becomes inoperable, in-mediate corrective measures must be taken since this sytem provides the major fire suppression capability of the plant. The requirement for twenty-four hour report to the Commission provides for prompt evaluation of the acceptability of the corrective measures to provide adequate fire suppression capability for the continued protection of the nuclear plant.
3.19/4.19 FIRE BARRIER PENETRATION SEALS The functional integrity of the fire barrier penetration seals ensures that fires will be confined or adequately retarded from spreading to adjacent portions of the facility. This design feature minimizes the possibility of a single fire rapidly involving several areas of the facility prior to detection and extinguish-ment. The fire barrier penetration seals are a passive element in the facility fire protection program and are subject to periodic inspections.
During periods of time when the seals are not functional, a continuous fire watch is required to be maintained in the vicinity of the affected seal until the seal is restored to functional status.
Fire barrier penetration seals include cable penetration barriers, fire doors, and fire dampers.
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