ML20041A013
| ML20041A013 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 02/02/1982 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Arkansas Power & Light Co |
| Shared Package | |
| ML20041A014 | List: |
| References | |
| DPR-51-A-062 NUDOCS 8202180475 | |
| Download: ML20041A013 (8) | |
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UNITED STATES y
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g NUCLEAR REGULATORY COMMISSION sg aj wAsHWGTON D.C.20555 Npe/
ARKANSAS POWER & LIGHT COMPANY DOCKET NO. 50-313 ARKANSAS NUCLEAR ONE. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.62 License No. DPR-51 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Arkansas Power and Light Company (the licensee) dated January 30, 1981, as supplemented September 22, 1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in lQ CFR Chapter I; The 'acility will operate in confomity with the application, f
B.
the provisions of the Act, and the rules and regulations of 4
the Comissi,on; 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 ac'tivities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The B;uance of this amendment is in accordance with 10 CPR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
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.2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.c.(2).of Facility Operating License No. OpR-51 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices
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A and B, as revised through Amendment No. 62, 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 the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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John. F.2Stolf, Chief 0 erating Reactors Branch #4 vision of Licensing '"-"~~~
Attachment:
. Changes. to the Technical Specifications Date of Issuance:
February 2,1982 8
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ATTACHMENT TO LICENSE AMENDMENT NO. 62 FACILITY OPERATING LICENSE NO. OPR-51 DOCKET NO. 50-313 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
38 38a 95 96 97 e
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l systems which will not remove more than one train of each system from service. Maintenance shall not be performed on components which would make the affected system train inoper-able for more than 24 consecutive hours.
Prior to initiating maintenance on any component of a train in any system, the redundant component of that system shall be demonstrated to be operable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the maintenance.
3.3.6 If the conditions of Specifications 3.3.1, 3.3.2, 3.3.3, 3.3.4 and 3.3.5 cannot be met except as noted in 3.3.7 below, reactor shutdown shall be initiated and the reactor shall be in hot shutdown condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />, and, if not corrected, in cold shutdown condition within an additional 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
3.3.7 Exceptions to 3.3.6 shall be as follows:
(A) If the conditions of Specification 3.3.l(F) cannot be met, reactor operation is permissible only during the succeed-ing seven days unless such components are sooner made operable, provided that during such seven days the other BWST level instrument channel shall be operable.
(B) If the conditions of Specification 3.3.3(D) cannot be met, reactor operation is permissible only during the succeed-ing seven days unless such components are sooner made operable, provided that during such seven days the other CFT instrument channel (pressure of level) shall be operable.
(C) If the conditions of Specification 3.3.4(A) cannot be met because one group of the required reactor building emer-gency cooling units is inoperable but both reactor build-ing spray systems are operable, restore the inoperable group of cooling units to operable status within 7 days or be in at least hot shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
(0) If the conditions of Specification 3.3.4(A) cannot be met because two groups of the required reactor building emergency cooling units are inoperable but both reactor building spray systems are operable, restore at least one group of cooling units to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least hot shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. Restore toth above required groups of cooling units to operable status within 7 days of initial loss or be in at least hot ishutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following -30 hours.
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38 Amendment No. 62 MF lh Er.
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l (E) If the conditions of Specification 3.3.4(A) cannot be met because one group of the required reactor building emer-gency cooling units are inoperable and one reactor build-ing spray system is inoperable, restore the inoperable spray system to operabie status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least hot shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
Restore the inoperable group cf. reactor building emergency cooling units to operable status within 7 days of initial loss or ba in at least hot shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
(F) If the conditions of Specification 3.3.4(A) cannot be met because any cooling unit of the required groups is inoperable because its associated fan is inoperable, verify that the operable cooling unit in that group has a service water flow rate a 1200 gpm through its cooling coils or restore the inoperable cooling unit to operable status within 7 days or be in at least hot shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
Bases The requirements of Specification 3.3.1 assure that below 350' F, adequate long term core cooling is provided. Two low pressure injection pumps are specified. However, only one is necessary to. supply emergency coolant to the reactor in the event of a loss,of-coola'nt accident.
.The post-accident reactor building cooling and long-term pressure reduc-tion may be accomplished by four cooling units, by two spray units or by a combination of one cooling unit and one spray unit.
Post-accident iodine removal may be acccmplished by one of the two spray system strings. The specified requirements assure that the required post-accident components are available for both reactor building cooling and iodine removal.
Specification 3.3.1 assures that the required equipment is operational.
The borated water storage tank is used for three purposes:
(A) As a supply of borated water for accident conditions.
(B) As an alternat,e supply of borated water for reaching cold shutdown. (2)'
As a supply of borated water for flooding the fuel transfer (C) ranal during refueling operation. (3)
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38a Amendment No.,26',
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i 4.5.2
. Reactor Building Cooling Systems Applicability App'ies to testing of the re^ actor building cooling systems.
Objective To verify that the reactor building cooling systems are operable.
Specification 4.5.2.1 System Tests 4.5.2.1.1 Reactor Building Spray System (a) Once every 18 months, a system test shall be conducted to demon-strate proper operation of the system. A test signal will be applied to demonstrate actuation of the reactor building spray i
system (except for reactor building inlet valves to prevent water entering nozzles).
(b) Station compressed air or smoke will be introduced into the spray headers to verify the availability of the headers and spray nozzles at least every five years.
(c) The test will be codsidered satisfactory if visual observation and control board indication verifies that all components have i
responded to the actuation signal properly.
4.5.2.1.2 Reactor Building Cooling System (a) At least once per 14 days, each reactor building cooling group shall be tested to demonstrate proper operation of the system.
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The test shall be performed in accordance with the procedure summarized below:
(1) Verifying a service water flow rate of > 1200 gpm to each j
group of cooling units.
(2) Chlorinating the service water during' the surveillance in 4.5.2.1.2.a.1 above, whenever service water temperature is between 60F and SOF.
, (b) At lea _st once per 31 days, each reactor building cooling group shall be' tested to demonstrate proper operation of the system.
The test shall be perforsed 'in accordanft with the procedure summarized below:
I (1) Starting (unless already operating) each operational cooling
'init f rom the control room.
i Amendment flo.,2( ~ 62
I (2) Verifying that each operational cooling unit operates for at least 15 minutes.
(c) Once every 18 months, a system test shall'be conducted to demon-strate proper operation of the system. The test shall be par-formed in ace.ordance with the procedure summarized below:
(1) A test signal will be applied to actuate the reactor. building cooling operation.
(2) Verification of the engineered safety features function of tSi service water system which supplies the reactor building alers shall be made to demonstrate operability of the ecolors.
(3) The test will be considered satisfactory if control board indication verifies that all components have responded to the actuation signal properly.
4.5.2.2 Component Tests 4.5.2.2.1 Pumps At intervals not to exceed 3 months the reactor building spray pumps shall be started and operated to verify proper operation.
Acceptable parformance will be indicated if the pump starts, operates for fif teen ~ minutes, and the discharge pressure and flow are within +10% of a point on the pump head curve.
4.5.2.2.2 Valves At intervals not to exceed three months each engineered safety features valve in the reactor building spray and reactor building cooling system cad each engineered safety features valve associ-ated with reactor building cooling in the service water system shall be tested to verify that it is operable.
Bases The reactor building cooling system and the reactor building spray system are redundant to each other in providing post-accident cooling of the reactor building atmosphere to prevent the building pressure from exceed-ing the design pressure. As a result of this redundancy in cooling capa-
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bility, the allevable out of service time requirements for the reactor building cooling system have been appropriately adjusted. However, the
' ~j allodable out of service time requirements for the reactor building spray system' have been maintained consistent Vith that asTigned other inoperable
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engineered safeguard equipment-since the reactor building spray system also provides a mechanism for removing iodine from the reactor building.
atmosphere.
Amendment No. J1F,'62
Service water chlorination is performed during reactor building cooler surveillance to prevent buildup of Asian clams in the coolers when service water is pumped through the cooling coils. This is performed when service water temperature is between 60F and 80F since in this water temperature range Asian clams can spawn and produce larva which could pass through service water system strainers.
The delivery capability of one reactor building spray pump at a time can be tested by opening the valve in the line from the borated water storage tank, opening the corresponding valve in the test line, and starting the corresponding pump. Pump discharge pressure and flow indication demon-strate performance.
With the pumps shut down and the borated water storage tank outlet closed, the reactor building spray injection val /es can each be opened and closed by operator action. With the reactor building spray inlet valves closed, low pressure air or smoke can be blown through the test connections of the reactor building spray nozzles to demonstrate that the flow paths a,re open.
The equipment, piping, valves, and instrumentation of the reactor building cooling system are arranged so that they can be visually inspected. The cooling units and associated piping are located outside the secondary con-crete shield. Personnel can enter the reactor building during power oper-ations to inspect and maintain.this equipment. The service water piping and valves outside the reactor building are inspectable at all times.
Operational tests and inspections will be performed prior to ir.itial startup.
Two service water pu=ps are normally operating. At least once per month ope' ration of one pu=p is shifted to the third pump, so testing vill be unne:es s ary'.'
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The reactor buildin6 fans are normally operating, so testing is unnecess ary.
Re ference FSAR, Section 6 l
Amendment flo.,23, 62 97
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