ML20235G888
| ML20235G888 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 09/24/1987 |
| From: | Calvo J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20235G874 | List: |
| References | |
| GL-84-15, TAC-55860, NUDOCS 8709300277 | |
| Download: ML20235G888 (10) | |
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j N..v...f OMAHA PUBLIC POWER DISTRICT DOCKET NO. 50-285 FORT CALHOUN STATION, UNIT NO. 1 AMENDMENT TO FACILIT'i OPERATING LICENSE Amendment No.111 License No. DPR-40 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by the Omaha Public Power District (the licensee) dated March 28, 1986 as supplemented April 9, 1986, March 13 and June 22, 1987, complies with the standards and require-ments of the Atomic Energy Act of 1954, as amended (the Act), and the Commission'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 (1) 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 Commission's regulations; D.
The issuance of this amendment will not be inimical to the comon
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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 Comission's regulations and all applicable requirements have been satisfied.
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' 2.
Accordingly, Facility Operating License No. OPR-40 is amended by changes to-the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Facility Operating License No.
DPR-40 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.111, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Q ' c{. [c GW f
Jose A. Calvo, Director Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: September 24, 1987
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ATTACHMENT TO LICENSE AMENDMENT NO.111 FACILITY OPERATING LICENSE NO. DPR-40 DOCKET NO. 50-285 h
Revise Appendix "A" Technical Specifications as indicated below. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Pages Insert Pages 2-25 2-25 2-26 2-26 3-9 3-9 j
3-10 3-10 3-58 3-58 3-59 3-59 3-60 3-60 i
1 1
- 2. 0 LIMITING CONDITIONS FOR OPERATION 2.4 Containment Cooling (Continued)
During power operation one of the components listed above (in addition to one raw water pump) may be inoperable.
If the inoperable component is not restored to operability within seven days, the reactor shall be placed in hot shutdown condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
If the inoper-able component is not restored to operability within an additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the reactor shall be placed in a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
(2) Modification of Minimum Requirements During power operation, the minimum requirements may be modified to allow a total of two of the components listed in a. and b. to be inoperable at any one time (in addition to one raw water pump).
Only two raw water pumps may be out of service.
If the operability l
of both components is not restored within 24. hours, the reactor shall be placed in a hot shutdown condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
If the operability of both components is not restored within an additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the reactor shall be placed in a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Any valves, interlocks and piping directly associated with one of the above components and required to function during accident conditions shall be deemed to be part of that component and shall meet the same requirements as for that component.
Any valve, interlock or piping associated with the containment cooling system which is not included in the above paragraph and which is required to function during accident conditions may be inoperable for a period of no more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
If operation is not restored within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the reactor shall be placed in a hot shutdown condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Basis The requirements of Section 2.3, Emergency Core Cooling System, apply to the specifications above with respect to the operability of the
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J Amendment No. O, 111 2-25
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2.0' LIMITING CONDITIONS FOR OPERATION 2.4 Containment Cooling (Continued) component cooling heat exchangers and shutdown heat exchangers.
A full-capacity diesel generator is connected to each of the two engineered safeguards 4.16-kV buses.
Three engineered safeguards 480-Volt double-ended load centers are provided; of the six transformers, three are-connected to each of the two 4.16-kV buses.
Two load centers are operated as two-bus-section units; the third is provided with a center bus manually transferable to either associated end section.
The. center bus section supplies HPSI Pump 51-20, CS Pump SI-3C and Charging Pump CH-1C any of which can thus be supplied from either 4.16-kV bus if required.
Threecomponentcoolingheatexchangegshavesufficier.,
capacity (withampleresey)toremove420x10 BTU /hr following a loss-of-coolant accident.
The containment sprays initially take Before this supply of water is exhausted (at least 24 minutes)g.
coolant from the safety injection and refueling water (SIRW) t the spray system is transferred to the recirculation mode and the pumps 4
take suction from the containment sump.
One shutdown cooling heat ex-changer is sufficient to satisfy the spra(33ystem requirements during the long-term containment cooling period In addition, in the un-likely event of the component cooling water supply being lost, raw watercanbeutilizedfordiregcoolingoftheshutdownheatexchangers and containment cooling coils.
The containment spray system is redundant with the containment air cooling function.gng and iodine removal system for the containment recirculation, co The spray system is sized such that two of the three spray pumps would T.imit the containment pressure to below the design value following a DBA without taking credit for g air coolers or the cooling capacity of the safety injection system.
Similarly, two cooling and filtering units or one cooling and filtering unit and pressureunderthesameconditionsastwospraypumps.gntainment both cooling units have the capability of limiting the The redundant cooling equipment provided to limit the containment pressure following a DBA is divided between the independent power supply systems.
The raw water and component cooling water pumps are similarly distributed on the 4.16-kV and 480 Volt buses to serve the above cooling groups.
Each cooling group has a design capacity equal to that required to restrict the containment pressure to below the design value.
In the event of a DBA, loss of normal power sources and failure of one diesel-generator to operate, better than one full group would be connected to the available diesel generator, thus providing more than ample reserve.
Any one unit removed from a given bus does not restrict the groups which can be connected to one diesel-generator from fulfilling their design function.
The removal of two l
units from buses which can be connected to one diesel generator could limit the capability of the associated cooling groups; therefore, to ensure availability of the power supply to the redundant equipment in the event of loss of normal power sources, the diesel generator serving this redundant equipment is in standby condition.
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i 3.0 SURVEILLANCE REQUIREMENTS j
3.7 Emergency Power System Periodic Tests Applicability i
Applies to periodic testing and surveillance requirements of the i
emergency power system.
Objective To verify that the emergency power system will respond promptly and properly when required.
Specifications The following tests and surveillance shall be performed as stated:
(1) Diesel' generators:
a.
Each diesel engine shall be started at least once per 31 days on a staggered basis. The engine shall be run with all protective devices operable.
The test shall verify that:
i i.
The diesel starts and accelerates to rated speed and 1
voltage in less than or equal to 10 seconds.
Normally, for the purpose of this surveillance testing, j
these diesel generator starts may be preceded by an engine prelube period and/or other warm-up procedures recommended by the manufacturer so that mechanical stress and wear on the engine is minimized.
However, at least once per 184 days in these surveillance tests, the 10 second diesel generator start shall be performed 1
from ambient conditions (cold start).
The signal initiated to start the diesel shall be varied from one test tgygnother to verify all manual and auto start circuits ii.
With the diesel running at rated speed and voltage, the
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generator shall be synchronized with the 4.16 KV bus and the i
diesel breaker manually closed from the electrical control l
Thgenerator shall then be loaded to at least the l
board.
KW rating and run for at least 60 minutes continuous before being off-loaded and the diesel breaker tripped.
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b.
The auto-start initiating circuit for each diesel shall be tested J
prior to each plar.t startup if not done during the previous week.
c.
Tests shall be conducted during each refueling outage to demonstrate the satisfactory overall automatic operation of each diesel system.
This test shall be conducted by:
L Amendment No. (I, 111 3-58
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^
3.0- SURVEILLANCE REQUIREMENTS
. 3.7 Emergency Power System Periodic Tests (Continued) 5 i..
Initiation of a simulated auto-start signal to verify that the diesel starts, followed by,
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ii.
Initiation of a simulated simultaneous loss of 4.16 KV supplies j
to bus 1A3 (1A4).
Proper operation will be verified by observa-j tion of:
(1) De-energization of bus 1A3 (1A4).
(2) Load shedding from bus-(both 4160 V and 480 V).
(3) Energization of bus 1A3 (1A4).
(4) Automatic sequence start of emergency load, and (5) Operation of > 5 minutes while its generator is loaded with the emergency load.
iii. Verification that emerge g loads do not exceed the 2000-HR KW rating of the engine, d.
Manual control of diesel generators and breakers shall also be verified during refueling shutdowns.
e.
Each diesel generator shall be given a thorough inspection on a refueling (R). frequency in accordance with the manufacturer's recommendations for this class of standby service.
f.
The fuel oil transfer pumps shall be verified to be operable each month.
(2) Station Batteries a.
Every month the voltage of each cell (to the nearest 0.01 volt),thespecificgravity,andtemperatureofapi{g}(4) cell in each battery shall be measured and recorded, b.
Every three months the specific gravity of each cell, the temper-ature reading of every fifth cell, and the amount of water added shall be measured and recorded.
During the first refueling outage and every third refueling outage thereafter the batteries shall be subjected to a rated load discharge test.
c.
At monthly intervals the third battery charger, which is capable of being connected to either of the two D.C. dis-tribution buses, shall be paralleled in turn to each D.C.
bus.
In each case, load shall be transferred to this re-serve battery charger by switching out the normal charger.
The reserve charger shall be run on load for 30 minutes on each bus and the system shall finally be returned to normal.
Amendment No. 24, 111 3-59 1
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- 3. 0 SURVEILLANCE REQUIREMENTS 3.7 Emergency Power System Periodic Tests (Continued) d.
During refueling shutdowns the correct function of all D.C.
emergency transfer switches shall be demonstrated by manual transfer of normal D.C. supply breakers at the 125 volt D.C.
distribution panels.
(3) Emergency Lighting The correct functioning of the emergency lighting system shall be verified at least once each year.
(4) 13.8 Kv Transmission Line The 13.8 KV transmission line will be energized and loaded to minimum shutdown requirements at each refueling outage following installation.
Basis The emergency power system provides power requirements for the engineered safety features in the event of a DBA.
Each of the two diesel generators is capable of supplying minimum required safety feature equipment from independent buses.
This redundancy is a factor in establishing testing intervals.
The monthly tests specified will demonstrate operability and load capacity'of each diesel generator.
These tests are conducted to meet the objectives of NRC Generic Letter 84-15 regarding the issue of reductions in cold fast starts.
For this reason, the test verifying a 10 second start will be conducted from ambient conditions once per 184 days for each diesel.
Other monthly tests will allow for manufacturer's recommended warm-up to reduce the mechanical stress and wear on the diesel engines.
The fuel supply and various controls are continuously monitored and alarmed for off-normal conditions.
At approximately yearly intervals (during refueling shutdowns) automatic starting on loss of off-site power and automatic load shedding, diesel connection, and loading will be verified.
At the same intervals, capability will be verified for manual emergency control of these functions from the diesel and switch gear rooms.
Considering system redundancy, the specified testing intervals for the station batteries should be adequate to detect and correct any malfunction before it can result in system malfunction.
Batteries will deteriorate with time, but precipitous failure is extremely unlikely.
The surveillance specified is that which has been demonstrated over the years to provide an indication of a cell becoming unserviceable long before it fails.
References (1) USAR, Section 7.3.4.2 (2) USAR, Section 8.4.1 (3) USAR, Section 8.3.4 (4) USAR, Section 8.4.2 Amendment No. 24,111 3-60 l
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