ML20080P297
| ML20080P297 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  (DPR-51-A-177) |
| Issue date: | 03/01/1995 |
| From: | Kalman G NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20080P301 | List: |
| References | |
| NUDOCS 9503070309 | |
| Download: ML20080P297 (11) | |
Text
(** " 8%,
O' UNITED STATES o
i
~i NUCLEAR REGULATORY COMMISSION
[
WASHINGTON, D.C. 200Ei6 p,
ENTERGY OPERATIONS INC.
DOCKET NO. 50-313 ARKANSAS NUCLEAR ONE. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 177 License No. DPR-51 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated June 22, 1994, 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 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 Commission; 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 license 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.
9503070309 950301 PDR ADOCK 05000313 P
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. DPR-51 is hereby amended to read as follows:
2.
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 177, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective 30 days following the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION M
George Kal
, Senior Project Manager Project Directorate IV-1 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: March 1, 1995 l
ATTACHMENT TO LICENSE AMENDMENT NO. 177 FACILITY OPERATING LICENSE NO. DPR-51 DOCKET NO. 50-313 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Aiaendment number and contain vertical lines indicating the area of change.
REMOVE PAGES INSERT PAGES 40 40 40a 40a 41 41 41a 41a 42b 42b 43c 43c 105 105 105a 105a
3.4 STEAM AND POWER CONVERSION SYSTEM Applicability Applies to the turbine cycle components for removal of reactor decay heat.
obiective To specify minimum conditions of the turbine cycle equipawnt necessary to assure the capability to remove decay heat from the reactor core.
Specifications 3.4.1 The reactor shall not be heated above 280*F unless the following conditions are met:
1 1.
Capability to remove decay heat by use of two steam generators.
Fourteen of the steam system safety valves are operable.
3.
A minimum of 11.1 feet (107,000 gallons) of water is available in Tank T41B.
4.
(Deleted) l S.
Both main steam block valves and both main feedwater isolation valves are operable.
3.4.2 Components required to be operable by Specification 3.4.1 shall not be removed from service for more than 24 consecutive hours.
If the system is not restored to meet the requirements of Specification 3.4.1 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 the 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 requirements of Specification 3.4.1 are not met 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 the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.4.3 Two (2) EFW trains shall be operable as follows:
1.
The motor driven EFW pump and its associated flow path shall be operable when the RCS is above CSD conditions and any Steam Generator is relied upon for heat removal.
2.
The turbine driven EFW pump and its associated flow path shall be 1
operable when the RCS temperature is 2 280'F.
~
- Except that during hydrotests, with the reactor suberitical, fourteen of the steam system safety valves may be gagged and two (one on each header),
may be reset for the duration of the test, to allow the required pressure for the test to be attained.
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~ Except that the surveillance testing of the turbine driven EFW pump shall be performed at the appropriate plant conditions as specified by Surveillance Requirement 4.8.1.
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Amendment No. M,M, M,M4,M4,177 40 1
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f 3.4.4 If tho cInditiens ep;cificd in 3.4.3 c nn t b3 mets 1.
With the motor' driven _ErW pump or its associated. flow path inoperable and RCS conditions above CSD and RCS temperature < 280*F and any steam Generator. relied upon for heat removal, immediately initiate action to restore the ETW train to operable status.
2 With the RCS temperature 2 280'! and one steam generator supply path to the turbine driven Ei"W pump inoperable, restore the steam generator supply path to operable scAtus within 7 days or be in Hot Shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce HC'.) temperature to < 280*r within thi next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
3.
With the RCS temperature 2 28M'F tir,.
onc YrW pump or its associated flow path inoperable, restore the CE9 tr5xa to operable status t
within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in Hot Shutdown v!.cSin 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and reduce RCS temperature to < 280'r within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
4.
With the RCS temperature 2 280'Fc both ETW pumps or their associated flow paths inoperable, and the Auxiliary Feedwater pump availabic, be in Hot Shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and reduce RCS temperature to < 280'r within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
5.
With the RCS temperature 2 280'F and both EFW pumps or their associated flow paths inoperable, and the Auxiliary Feedwater pump unavailable, immediately initiate action to restore one EFW train or the Auxiliary Feedwater pump to operable status. LCO 3.0.3 and all other LCO Required Actions requiring mode changes are suspended until one EFW train or the Auxiliary Feedwater pump is restored to operable status.
i Amendment No. 64,44,174,177 40a
7~,ng - -
1 Bases The Emergency Feedwater (ErW) system is designed to' provide flow sufficient to remove heat load equal to 34 percent full power operation. The system minimum flow requirement to the steam generator (s) is 500 gpm.
This takes into account a single failure, pump recirculation flow, seal leakage and pump wear.
In the event of loss of main feedwater, feedwater is supplied by the emergency feedwater pumps, one which is powered from an operable emergency bus and one which is powered from an operable steam supply system.
Both EFW pumps take suction from tank T418.
Decay heat is removed fram a steam generator by steam relief through the turbine bypass,' atmospheric dump valves, or safety valves.
Fourteen of the steam safety valves will relieve the necessary amount of steam for rated reactor power.
The EFW system is considered to be operable when the components and flow paths required to provide ErW flow to the steam generators are operable.
This requires that the turbine driven EFW pump be operable with redundant steam supplies from each of the main steam lines upstream of the MSIVs (CV-2617 and CV-2667) and capable of supplying EFW flow to either of the two steam generators. The motor driven EFW pump and associated flow path to the ErW system is -1so required to be operable. The piping, valves, instrumentati and controls in the required flow paths shall also be operable.
P.
CrW t rein, which includes the motor driven EFW pump, is l
required operable when above CSD and below 280'r with any steam generator.siied upon for heat removal. This is because of reducea heat removal requirements, the short duration ErW would be required, and the insufficient steam supply available in this condition to power the turbine driven EFW pump.
When one of the required ErW trains is inoperable, action must be taken to restore the train to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
This condition includes loss of the steam supply to the turbine driven EFW pump. The 72' hour completion time is reasonable, based on the redundant capabilities afforded by the ErW system, time needed for repairs, and the low probability of a DBA occurring during this time period.
With two EFW trains inoperable, the unit must be placed in a mode in which the LCO does not apply using the Auxiliary Feedwater pump. With RCS temperature < 200*F the Decay Heat Removal system may be placed in operation.
'With both EFW trains inoperable and the Auxiliary Feedwater pump mavailable, the unit is in a seriously degraded condition with only limited means for conducting a cooldown using nonsafety grade equipment.
In such a condition, the unit should not be perturbed by any action, including a power change, that might result in a trip.
The seriousness of this condition requires that action be started immediately to restore at least one EFW pump or the Auxiliary Feedwater pump to Operable status.
LCO 3.0.3 is not applicable, as it could force the unit into a less safe condition.
Amendment No. M,M,474,177 41 l
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I Th3 minimum amount of water in tank T41B would be adequate for about 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> of operation. This is based on the estimate of the average emergency flow to a steam generator being 390 gpm. This operation time with the volume of water specified would not be reached, since the decay heat removal system could be brought into operation within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or less.
A portion of tank T41B is protected om tornado missiles. The protected volume is sufficient to provide a thirty minute supply of water. This thirty minute period is suf ficient to allow manual oporator action, if required, to transfer suction of the emergency feedwater pumps to service water.
i Amendment No. M,4M,177 41a
h 3.5.1.13 Tha S:icmic Monitoring Instrumentaticn chn11 b3 eparrblo with a ninimum measurement range of 0.01 - 1.0 g for Triaxial Time -
i History Accelerographs, 0.05 - 1.0 g for Triaxial Peak i
Accelerographs, and 2-25.4 Hz for Triaxial Response Spectrum Recorders.
3.5.1.14 The Main Steam Line Radiation Monitoring Instrumentation shall be operable with a minimum measurement range from 10~1 to j
104 mR/hr, whenever the reactor is above the cold shutdown condition.
3.5.1.15 Initiate functions of the EFIC system which are bypassed at cold shutdown conditions shall have the following minimum operability conditions:
- a. " low steam generator pressure" initiate shall be operable when the main steam pressure exceeds 750 psig.
- b. " loss of 4 RC purps" initiate shall be operable when neutron flux exceeds 10% power.
3.5.1.16 The automatic steam generator isolation system within EFIC shall be cperable when main steam pressure is greater than 750 psig.
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Amendment No.
4-M, MG, M4J 77 42b t
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Th3 CPERABILITY cf th3 S:icmic Monitoring Inctrumentction cnnuras thtt sufficient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features important to safety.
This capability is required to permit comparison of the measured response to that used in the design basis for the facility to determine if plant shutdown is l
required pursuant to Appendix "A" of 10CFR Part 100. The instrumentation is consistent with the recommendations of Safety Guide 12, " Instrumentation for Earthquake," published March 19, 1971, and NUREG-0800 Section 3.7.4,
" Seismic Instrumentation."
To support loss of main feedwater analyses, steam line/feedwater line break analyses, SBLOCA analyses, and NUREG-0737 requirements, the EPIC system is designed to automatically initiate EFW when:
1.
all four RC pumps are tripped 2.
both main feedwater pumps are tripped 3.
the level of either steam generator is low
{
)
l 4.
either steam generator pressure is low i
5.
ESAS ECCS actuation (high RB pressure or low RCS pressure)
The EFIC system is also designed to isolate the affected steam generator on a steam line/feedwater line break and supply EFW to the intact generator according to the following logic:
If both SG's are above 600 psig, supply EFW to both SG's.
If one SG is below 600 psig, supply EFW to the other SG.
1 If both SG's are below 600 psig, but the pressure difference i
between the two SG's exceeds 100 psig, supply EFW only to the SG i
with the higher pressure.
If both SG's are below 600 psig and the pressure difference is less than 100 psig, supply EFW to both SG's.
At cold shutdown conditions all EFIC initiate and isolate functions are bypassed except low steam generator level initiate. The bypassed functions will be automatically reset at the values or plant conditions identified in Specification 3.5.1.15.
"Less of 4 RC pumps" initiate and " low steam generator pressure" initiate are the only shutdown bypasses to be manually initiated during cooldown.
If reset is not done manually, they will automatically reset. Main feedwater pump trip bypass is automatically removed above 10% power.
REFERENCE FSAR, Section 7.1 FSAR, Section 2.7.6 Amendment No.
444,177 43c
4.0 EMERGENCY FEEDWATER PUMP TESTING Applicability Applies to the periodic testing of the turbine and electric motor driven emergency feedwater pumps.
objective i
To verify that the emergency feedwater pump and associated valves are operable.
Specification 4.6.1 Each EFW train shall be demonstrated operabler a)
By verifying on'a STAGGERED TEST RASIS:
I i
1.
at least once per 31 days or within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> af ter reaching the Hot Shutdown condition following a plant heatup and prior to criticality, that the turbine-driven pump starts, operates for a minimum of 5 ndnutes and develops a discharge pressure of 21200 psig at a flow of 2 500 gpm through the test loop flow path.
2.
at least once per 31 days by verifying that the motor driven EFW pump starts, operates for a minimum of 5 minutes and develops a discharge pressure of 21200 psig at a flow of 2 500 gpm through the test loop flow path.
l b)
At least once per 31 days by verifying that each valve (manual, power operated or automatic) in each EFK flowpath that is not locked, sealed, or otherwise secured in position, is in its correct position.
c)
Prior to relying upon any steam generator for heat removal whenever the plant has been in CSD or less for > 30 days, verify proper alignment of each manual valve in each required EFW flow path, which if ndspositioned may degrade EFW operation, from the 'Q' condensate storage tank to each steam generator.
d)
At least once per 92 days by cycling each motor-operated valve in each flowpath through at least one complete cycle.
e)
At least once per 18 months by functionally testing each EFW train and:
1.
Verifying that each automatic valve in each flowpath actuates automatically to its correct _ position on receipt of an actual or simulated actuation signal.
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Amendment No. M, M,M,4M, $ 74,177 105
V' '_
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2..
Verifying that the automatic steam supply valves 3*
. associated with the steam turbine driven EFW pump actuate to their correct positions upon receipt of an j
3 actual or simulated actuation signal.
This test is not required to be performed until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after reaching j
800 psig in the steam generators.
3.
Verifying that the motor-driven'ETW pump starts automatically upon receipt of an actual or simulated l l actuation signal.
4.
Verifying that feedwater is delivered to each steam
)
generator using the electric motor-driven ErW pump.
l 5.
Verifying that the EFW system can be operated manually by over-riding automatic signals to the EFN valves.
l Bases The monthly testing frequency will be sufficient to verify that both emergency feedwater pumps are operable. Verification of correct operation will be made both from the control room instrumentation and direct visual observation of the pumps. The cycling of the emergency valves assures j
valve operability when called upon to function. Testing'of the turbine driven EFW pump is delayed until suitable test conditions are established. :This deferral is required because there is insufficient. steam pressure to perform the test at 280*F.
Testing may occur at a lower steam generator pressure if operational experience shows that sufficient steam pressure to perform the test l
exists.
i surveillance Requirement 4.8.1.c ensures that the ErW system is properly aligned-
[
by verifying the flow paths to each steam generator prior to. relying upon any l
steam generator for heat removal after more than 30 days in Cold Shutdown or i
below, operability of the EFW flow paths must be demonstrated before sufficient.
core heat is, generated that would require the operation of the EFW system during
}
a subsequent shutdown. This requirement is reasonable, based on engineering judgment, in view of other administrative controls to ensure that the flow paths are operable. To further ensure ErW system alignment, flow path operability is verified following extended outages to determine no adsalignment of valves has occurred. This SR ensures that the flow path from the 'Q' CST to the steam generators is properly aligned.
I The functional test, performed once every 18 months, will verify that the i
i flow path to the steam generators is open and that water reaches the steam j
generators from the emergency feedwater system. The test is done during shutdown to avoid thermal cycle to the emergency feedwater nozzles on the steam generator due to the icwer temperature of the emergency feedwater.
i The automatic actuation circuitry testing and calibration will be performed per surveillance specification 4.1, and will be sufficient to assure that this circuitry will perform its intended function when called upon.
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i Amendment No. 34.50,41,177 105a j
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