ML20198S597
| ML20198S597 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 12/31/1998 |
| From: | Nick Hilton NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20198S601 | List: |
| References | |
| NUDOCS 9901110369 | |
| Download: ML20198S597 (6) | |
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j NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. 306eH001 49.....,o j
ENTERGY OPERATIONS INC.
DOCKET NO. 50-313 J
ARKANSAS NUCLEAR ONE. UNIT NO.1
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AMENDMENT TO FACILITY OPERATING LICENSE g
Amendment No.194 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 May 31,1996, 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; 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.
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9901110369 981231 PDR ADOCK 05000313 P
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Accordingly, the license is amended by changes to the Technical Specifications as j
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 t
Amendment No. 194, are hereby incorporated in the license. The licensee l
shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
. / /ll gr MO Nicholas D. Hilton, Project Manager Project Directorate IV-1 Division of Reactor Projects !!!/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: December 31, 1998 L
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l ATTACHMENT TO LICENSE AMENDMENT NO.194 FACILITY OPERATING LICENSE NO. DPR.St.
t-DOCKET NO. 50-313 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain verticallines indicating tb r area of change.
l REMOVE PAGES INSERT PAGES g
68 68 69 69 72d 72d 3
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Othor chtnnsic cro'aubject only to " drift" orrors inducsd within ths
.instrumentatien itoolf and, conscquantly, een toloreto longar intervals between calibrations.
Process system instrumentation errors induced by j.
drift can be expected to remain within acceptable tolerances if recalibr,ation is performed once every 18 months.
Substantial calibration shifts within a channel (essentially a channel failure) will be revealed during routine checking and testing procedures.
l Thus, minimum calibration frequencies for the nuclear flux (power range) l channels, and once every 18 months for the process system channels is l
considered acceptable.
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Testing on-line testing of reactor protective channel and EFIC channels is reettred once every 4 weeks on a rotational or staggered basis. The rotation scheme is designed to reduce the probability of an undetected failure' existing within the system and to Minimize the likelihood of the
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same systematic test errora being introd ier d into each redundant channel.
l All reactor protective channels will be tested before startup if the individual channel rotational frequency has been discontinued or if outage activities could potentially have affected the operability of one or more channels. A rotation will then be established to test the first Channel one week after startup, the second channel two weeks after startup, the third channel three weeks after startup, and the fourth Channel four weeks after startup.
The established reactor protective system instrumentation and EFIC test cycle is continued with one channel's instrumentation tested each week.
Upon detection of a failure that prevents trip action, all instrumentation j
associated with the protective channels will be tested after which the l
rotational test cycle is started again.
If actuation of a safety channel occurs, assurance will be required that actuation was within the limiting I
safety system setting.
The protective channels coincidence logic and control rod drive trip breakers are trip tested every quarter. The trip test checks all logic l
-combinations and is to be performed on a rotational basis. The logic and breakers of the four protective channels shall be trip tested prior to l
startup and their individual channels trip tested on a cyclic basis.
l Discovery of a failure requires the testing of all channel logic and breakers, after which the trip test cycle is started again.
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Am a dment No u,M,194 68 Revised by NRC Letter Dated g' ' g
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Table 4.1-1 Instrument Surveillance Requirements channel
Description:
Check Test Calibrate Remarks
- 1.
Protective Channel NA Q
NA
'l Coincidence Logic 2.
Control Rod Drive NA Q(1)
NA (1)' To include independent testing l
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Trip Breaker
.of the shunt and undervoltage.
trip attachments.
3.
Power Range Amplifier NA NA T/W(1)
(1)
Heat balance calibration twice
. weekly under steady state operating conditions, daily under non-steady state opera-ting conditions.
4.
Power Range Channel S
M M(1) (2)
(1)
Using core instrumentation.
M(1)
(2) Axial offset upper and lower chambers monthly and after each startup if not done previous week.
5.
Intermediate Range Channel S
P/M NA 6.
Source Range Channel S(l)
P NA (1) When in service.
7.
Reactor Coolant Temperature S
M R
Channel 8.
High Reactor Coolant S
M R
Pressure Channel i
i 9.
Low Reactor Coolant S
M R
Pressure Channel
- 10. Flux-Reactor Coolant Flow S
M R
Comparator 3
- 11. Reactor Coolant Pressure S
M R
Temperature Comparator
- 12. Pung Flux Comparator S
M R
Amendment No. 60,4M,194 69 h
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e Table 4.1-1 (Cont.)
Channel Description Check Test Calibrate Resnarks d.
SG A High Range Leve'l S
M R
High-high e.
SG B High Range Level S
M R
High-high
- 57. Containment High Range D
M R
Radiation Monitors
- 58. Containment Pressure-High M
NA R
- 59. Containment Water Level-Wide M
NA R
Range
- 60. Low Temperature Overpressure NA R
R Protection Alarm Logic
- 61. Core-exit Thersnoccuples M
NA R
62 Electronic (SCR) Trip Relays NA Q
NA l
63 RVLMS M
NA R
64 HLLMS M
NA R
NOTE:
S - Each Shift T/W - Twice per Week R - Once every 18 months W - Weekly Q-Quarterly PC - Prior to going Critical if not M - Monthly P-Prior to each done within previous 31 days D - Daily startup if not done NA - Not Applicable previous week SA - SA Twice per Year 7
B/M - Every 2 months i
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i Amendment No. Gh &4,%,444,444, 72d 4M,4M,194 1
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