ML20044B910
| ML20044B910 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 03/06/1993 |
| From: | Hubbard G Office of Nuclear Reactor Regulation |
| To: | Entergy Operations |
| Shared Package | |
| ML20044B911 | List: |
| References | |
| DPR-51-A-163, GL-83-037, NPF-06-A-145 NUDOCS 9303120165 | |
| Download: ML20044B910 (18) | |
Text
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p Krog'o UNITED STATES T,,
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p, NUCLEAR REGULATORY COMMISSION
'E WASHINGTON, D. C. 20555
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ENTERGY OPERATIONS. INC.
DOCKET NO. 50-313 ARKANSAS NUCLEAR ONE. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.163 License No. DPR-51 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated September 28, 1992, as supplemented by letter dated January 26, 1993, 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 accorda.nce with 10 CFR Part 51 of the Commission's regulations and all arglicable requirements have been satisfied.
t 9303120165 930306 ADOCK0500g3 PDR 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.163, 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 from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
,9]p p W
George T. Hubbard, Acting Director i
Project Directorate IV-1 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 6, 1993 t
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i ATTACHMENT TO LICENSE AMENDMENT NO.163 FACIllTY OPERATING LICENSE NO. DPR-51 DOCKET NO. 50-313 i
Revise the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment' number and contain vertical lines indicating the area of change.
REMOVE PAGES INSERT PAGES 42b 42b 45d2 45d2 45h 45h 71 71 72 72 146b 146b i
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3.5.1.13 The Seismic Monitoring Instrumentation shall be operable with a minimum measurement range of 0.01 - 1.0 g for Triarial Time -
History Accelerographs, 0.05 - 1.0 g for Triarial Peak Accelerographs, and 2-25.4 Hz for Triaxial Response Spectrum Recorders.
A 3.5.1.14 The Main Steam Line Radiation Monitoring Instrumentation shall be operable with a minimum measurement range from 10-8 to 10' mR/hr, whenever the reactor is above the cold shutdown condition.
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Anendment No. 111, Jet, 163 42b f
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Tabic 3.5.1-1 (cent'd)
OTHtR SAFETY REY.ATED SYSTEMS (Cont'd) 1 2
3 4
5 l
No. of Operator action channels Hin.
Min.
if conditions of No. of for sys-operable degree of column 3 or 4 Functional Unit channels tem trio channels redundanr.I _suunn be met I
c.
Triaxial Response-Spectrum Recorders 1.
2XR-8350, Unit 2 Containment 1
N/A 1
0 Note 27 Base Slab, Elev. 335' 6" (0/S Containment)
I 15.
Reactor Vessel Level Monitoring System 2
N/A 2
0 Note 28, 29 16.
Hot Leg Level Measurement System (HLLMS) 2 N/A 2
0 Note 28, 29 17.
Main Steam Line 1 / steam line N/A 1/ steam line O
Note 30 Radiation Monitors
'l Amendment No. JJJ 163 45d2
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Tabis 3.5.1-1 (cont'd)
- 28. With the number of OPERABLE channels one less than the minimum number of channels required to be OPERABLE:
a.
If repairs are feasible, restore the inoperable channel to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, b.
If repair is not feasible without shutting down, operation may continue and a special report pursuant to specification 6.12.5 shall be submitted to the NRC within 30 days following the failure; describing the action taken, the cause of the inoperability, and the plans and schedules for restoring the channel to OPERABLE stetus during the next scheduled refueling outage.
- 29. With the number of OPERABLE channels two less than the minimum channels required to be OPERABLE:
a.
If repairs are feasible, restore at least one inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b.
If repair is not feasible without shutting down, operation may continue and a special report pursuant to specification 6.12.5 shall be submitted to the NRC within 30 days following the failure; describing the action taken, the cause of the inoperability, and the plans and schedules lI for restoring the channels to OPERABLE status during the next scheduled refueling outage.
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- 30. With the number of OPERABLE Channels less than required by the Minimum Channels OPERABLE requirements, initiate the preplanned alternate method of monitoring the appropriate parameter (s), within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and:
- 1) either restore the inoperable Channel (s) to OPERABLE status within 7 days of the event, or
- 2) prepare and subsit a Special Report to the Commission pursuant to Specification 6.12.5 within 14 days following the event outlining the action taken, the cause of the inoperability and the plans and i
schedule for restoring the system to OPERABLE status.
i Amendment No. JJJ 163 45h
[*W Table 4.1-1 (Cont'd)
Channel Descriotion Check Inst Calibrate Remarks 20.
Reactor Building Spray System NA M(1)
NA (1) Including RB spray pump, System Logic Channels spray valves, and chen.
add, valve logic channels.
21.
Reactor Building Spray System Analog Channels a.
Reactor Building Pressure Channels NA M
R 22.
Pressurizer Temperature Channels S
NA R
i 23.
Control Rod Absolute Position S(1)
NA R
(1) Compare with Relative Position Indicator.
l 24.
Control Rod Relative Position S(1)
NA R
(1) Check with Absolute Position
~l Indicator.
25.
Core Flooding Tanks a.
Pressure Channels S
NA R
b.
Level Channels S
NA R
26.
Pressurizer Level Channels S
NA R
27.
Makeup Tank Level Channels D
NA R
28.
Radiation Monitoring Systems (1) Check functioning of self-checking other than containment high feature on each detector, range monitors (item 57) a.
Process Monitoring System S
Q R
b.
Area Monitoring System S
M(1)
R c.-
Main Steam Line Radiation Monitors S
M R
Amendment No. J A, J26 163 71
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Table 4.1-1 (Cont.)
l Channel Description Check Test Calibrate Remarks 1
- 29. High and Low Pressure NA NA R
Injection Systems: Flow Channels
- 30. Decay ;iest removal S(1)(2)
M(1)(3) R (1)
Includes RCS Pressure Analog Channel system isolation valve (2) Includes CFT 1 solation Valve Position automatic closure and (3) At least once every refueling shutdown, interlock sfstem with Reactor Coolant System Pressure greater than or equal to 200 psig, but less than 300 psig, verify automatic l
Isolation of the decay beat removal system from the Reactor Coolant System on high Reactor Coolant System pressure.
- 31. Turbine overspeedtrip NA R
NA (1) The provisions of Specification 4.0.4 mechanism are not applicable.
- 32. Diesel generator M
Q NA protective relaying startin; interlocks and circuitry
- 33. Off-site power undervoltage W
R(1)
R(1)
(1) Shall be tested during refueling and protective relaying shutdown to demonstrate selective interlocks and circuitry load shedding interlocks function during manual or automatic trans-fer of Unit 1 auxiliary load to Startup Transformer No. 2.
- 34. Borated water storage W
NA R
tank level indicator
- 35. Reactor trip upon loss M
PC R
of main feedwater circuitry Amendment No. 4 J7, 59, SP, 67, 7J, 152 72
/// 163
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b.
Inoperable Fire Detection Instrumentation 1.
Inoperable Fire Suppression Systems J.
Degraded Auxiliary Electrical Systems, Specification 3.7.2.H.
k.
Inoperable Reector Vessel Level Monitoring Systems, Table 3.5.1-1 i
1.
Inoperable Hot Leg Level Measurement Systems. Table 3.5.1-1 Inoperable Hair; Steam Line Radiation Monitors, Specification 3.5.1, m.
Table 3.5.1-1.
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b Amendment No. JJE, JJJ,ggs 163 146b
fp UNITED STATES NUCLEAR REGULATORY COMMISSION n
h WASHINGTON, D. C. 20$55
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ENTERGY OPERATIONS. INC.
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DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE. UNIT NO 2 P
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 145 License ho. NPF-6 i
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated September 28,.1992, as supplemented by letter dated January 26, 1993, 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:
(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 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.
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragras' ? C.(2) of Facility Operating License No. NPF-6 is hereby amended.to cca is follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.145, 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 from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
),ifL dW George T. Hubbard, Acting Director Project Directorate IV-I Division of Reactor Projects - III/IV/V Office of Nuclear Reacter Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 6, 1993 I
9
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i ATTACHMENT TO LICENSE AMENDMENT NO. 145 FACILITY OPERATING LICENSE NO. NPF-6 DOCKET NO. 50-368 Revise the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain docume,
.:ompleteness.
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REMOVE PAGES INSERT PAGES 3/4 3-25 3/4 3-25 3/4 3-26 3/4 3-26 3/4 3-27 3/4 3-27 6-19a 6-19a r
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TABLE 3.3-6 RADIATION MONITORING _ INSTRUMENTATION MINIMUM CHANNELS APPLICABLE ALARM / TRIP MEASUREMENT INSTRUMENT OPERABLE MODES
_SETPOINT RANGE ACTION 1.
AREA MONITORS
- 1 F
a.
Spent Fuel Pool Area Monitor i
Note 1 5 1.5x10 8 R/hr 10 * - 101 R/hr 13 b.
Containment High Range 2
1, 2, 3 & 4 Not Applicable 1 - 10' R/hr 18 2.
PROCESS MONITORS a.
Containment 1.
Gaseous Activity a) Purge & Exhaust Isolation 1
5&6 5 2 x background' 10 - 10' cpm 16 b) RCS Leakage Detection 1
1, 2, 3 & 4 Not Applicable 10 - 10' cpm 14
- 11. Particulate Activity a) RCS Leakage Detection 1
1, 2, 3 & 4 Not Applicable 10 - 10' cpm 14
.f-b Control Room Ventilation intake Duct Monitor 1
ALL MODES 5 2 x background 10 - 10' cpm 17 e
c.
Main Steen Line 1/ Steam 1, 2, 3,'& 4 Not Applicable 10'8 - 10' mR/hr 19 Radiation Monitors Line Note 1 - With fuel in the spent fuel pool or build.ing ARKANSAS - UdIT 2 3/4 3-25
. Amendment No. $$, JJ6.145
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TABLE 3_3-6 (Continund)
TABLE NUTATION ACTION 13 -
With the number of channels OPERABLE less t han required by the Minimum Channels OPERABLE requirement, perform area surveys of the monitored area with portable monitoring instrumentation at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ACTION 14 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.6.1.
ACTION 16 -
With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, complete the following:
- a. If performing CORE ALTERATIONS or moving irradiated fuel within the reactor building, secure the containment purge system or suspend CORE ALTERATIONS and movement of irradiated fuel within the reactor building.
- b. If a containment PURGE is in progress, secure the containment purge system.
- c. If continuously ventilating, verify the SPING monitor operable or perform the ACTIONS of 3.3.3.9, or secure the containment purge system.
ACTION 17 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate and maintain operation of the control room emergency ventilation system in the recirculation mode of operation.
ACTION 18 -
With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, (1) either restore the inoperable channel to OPERABLE status within 7 days or (2) prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days following the event, outlining the action taken, the cause of the inoperability, and the picts and schedule for restoring the system to OPERABLE status. With both channels inoperable, initiate alternate methods of monitoring the containment radiation level within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in addition to the actions described above.
ACTION 19 -
With the number of OPERABLE Channels less than required by the Minimum Channels OPERABLE requirements, initiate the preplanned siternate method of monitoring the appropriate parameter (s), within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and:
- 1) either restore the inoperable Channel (s) to OPERABLE status within 7 days of the event, or
- 2) prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 14 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring l
the system to OPERABLE status.
ARKANSAS - UNIT 2 3/4 3-26 Amendment No. f), 110 145
6 TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REOUIREMENTS CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENl
_.GILECJL CALIBRAllqN TEST REQUIRED._
1.
AREA MONITORS a.
Spent Fuel Pool Area Monitor S
R M
Note 1 b.
. Containment High Range S
R Note 4 M
1, 2, 3, & 4 2.
PROCESS' MONITORS a.
Containment
- 1.. Gaseous Activity a) Purge &-Exhaust Isolation Note 2 R
Note 3 5&6 b) RCS Leakage Detection S
R H
1, 2, 3, & 4 11.
Particulate Activity a) RCS Leakage Detection S
R H
1, 2, 3,.& 4 b.
Control Room Ventilation Intake Duct Monitor S
R M
ALL NODES.
c.
Main Steam Line Radiation S
R M
1, 2, 3, & 4 Monitors Note 1 - With fuel in the spent fuel pool or building.
' Note 2 - Within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to itiating containment purge operations and at least.once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during containment purge operations.
Note 3 - Within.31 days prior to initiating containment purge operations and at least once per 31 days during containment purge operations.
Note 4 - Acceptable criteria for calibration are provided in Table _ II.F.1-3 of NUREG-0737.
ARKANSAS UNIT 2 3/4 27-Amendment No.'$$, 7)#'145
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INSTRUMENTATION
-5 INCORI DETECTORS i
LIMITING OORDITION FOR OPERATf0N i
3.3.3.2 The incore detection system shall be OPERABLE with:
i At least 75% of all incere detectors with at least one incore s.
detector in each quadrant at each level, and
. b.
At least 75% of all incore detector locations, and Sufficient operable incere detectors to perfers at least six tilt c.
estimates with at least one tilt estimate at mach of three levels.
i An OPERABLE incore detector location shall consist of a fuel assembly containing either a fixed detector string with a minimum of three OPERABLE rhodium detectors or an OPERABLE movable incore detector capable of mapping the location.
A tilt estinate can be made from two sets of symmetric pairs of incore detectors. Two sets of symmetric pairs of incore detectors are formed by two pairs of diagonally opposite symmetric incore detectors, one incore detector per quadrant.
4 APPLICAPILITY: When the incore detection system is used for monitoring the AZIMUTHAL POWER TILT, radial peaking factors, local power density or DNB ma rgin.
ACTION:
Vith the incere detection system inoperable, do not use the system for the above applicable monitoring or calibration functions. The provisions of Specification 3.0.3 are not applicable.
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srPVElitANCE REOUIPFvrNTS i
4.3.3.2 The incere detection system shall be demonstrated OPERABLE:
a.
By performance of a CHANNEL CRECK within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to its use and at least once per 7 days thereafter when required for monitoring the AZIMUTHAL POWER TILT, radial peaking factors, local power density or DNB margia.
i b.
At least once per 18 months' by performance'of a CRANNEL i
CALIBRATION operation which exempts the neutron detectors but includes all electronic coeponents. The neutron detectors shall be calibrated prior to installation in the reactor core.
.i ARKANSAS - UNIT 2 3/4 3-28 Amendment No. JJ, 134__
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ADMINISTRATIVE CONTROLS SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Administrator of the Regional Office within the time period specified for each report. These reports.shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specifications I
- a. ECCS Actuation, Specifications 3.5.2 and 3.5.3.
- b. Inoperable Seismic Monitoring Instrumentation, Specifica-tion 3.3.3.3.
- c. Inoperable Meteorological Monitoring Instrumentation, Specifica -
tion 3.3.3.4.
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- d. Seismic event analysis, Specification 4.3.3.3.2.
- e. Inoperable Fire Detection Instrumentation
- f. Inoperable Fire Suppression Systems
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- g. Deleted.
- h. Radioactive Effluents Specifications 3.11.1.1, 3.11.1.2, f
3.11.1.3, 3.11.2.2, 3.11.2.3, 3.11.2.4, 3.11.2.5, and 3.11.3.
This report shall include the following:
1)
Description of occurrence.
2)
Identify the cause(s) for exceeding the limit (s) 3)
Explain corrective action (s) taken to mitigate occurrence.
1 4)
Define action (s) taken to prevent recurrence.
i 5)
Summary of consequence (s) of occurrence.
6)
Describe levels exceeding 40CFR190 zu accordance with l
10CTR20.40S(c).
- 1. Inoperable Containment Radiation Monitors.
Specification 3.3.3.1.
- j. Steam Generator Tubing Surveillance -- Category C-3 Results, I
Specification 4.4.5.5.
- k. Maintenance of Spent Fuel Pool Structural Integrity, Specification 3.7.12.
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- ARKANSAS - UNIT 2 6-19 Amendment No. 68,f3,92, 92,132-4 i
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ADMINISTRATIVE CONTROLS 1.
Radiological Environmental Monitoring Sample Analysis, Specification 3.12.1.
Unplanned Offsite Release during one bour period of 1) more than m.
1 curie of radioactive material in liquid effluents, 2) more than 150 curies of noble gas in gaseous affluents, or 3) more than 0.05 curies of radiciodine in gaseous effluents. This e
report shall be submitted within 30 days of the occurrence of the event and shall include the following information:
l l
1.
Description of the occurrence.
I 2.
Identify the cause(s) of ' exceeding the Ifmit(s).
3.
Explain corrective action (s) taken to mitigate occurrence.
4.
Define action (s) taken to prevent recurrence.
5.
Summary of the consequence (s) of occurrence.
}
Inoperable Reactor Vessel Level Honitoring System (RVLMS),
n.
Specification 3.3.3.6, Table.1.3-10 Item 14.
Inoperable Main Steam Line Radiation Honitors, Specification 3.3, o.
Table 3.3-6.
SEMI-ANFUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT
- l 6.9.3 Routine radioactive effluent release reports covering the operating of the unit during the previous 6 months of operations shall be submitted l
within 60 days af ter January 1 and July 1 of each year.
- A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for enits with separate radwaste system, the submittal shall specify the releases of radioactive material from each unit.
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1 ARKANSAS - UNIT 2 6-19a Amendment No. 71, 74.JJ) 145
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