ML20204H737
| ML20204H737 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 03/23/1999 |
| From: | Nolan M NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20204H740 | List: |
| References | |
| NUDOCS 9903290148 | |
| Download: ML20204H737 (4) | |
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UNITED STATES I
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NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 30eedM201
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ENTERGY OPERATIONS. INC.
DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 202 License No. NPF-6 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated February 25,1999, 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 caducted in compliance with the Commitsion's regulations; D.
The issuance of this license amendment will not be inimical to the common defense and security or to.he health and safety of the public; and E.
The issuance of this arr endment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
9903290148 990323 PDR ADOCK 05000368 P
. 2.
Accordingly, the license is amended by changes to the Technical Spe, cations as indicated in the attachment to th!s license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF 6.s hereby amended to read as follows:
- 2. Technical Soecifich The Technical /aecifications contained in Appendix A, as revised through j
Amendment t N. 202, are hereby incorporated in the license. The licensee 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 W.
M. Christopher Nolan, Project Manager Project Directorate IV-1 Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: March 23, 1999 4
ATTACHMENT TO LICENSE AMENDMENT NO. 202 FACILITY OPERATING LICENSE NO. NPF-6 DOCKET NO. 50-368 Replace the following page of the Appendix "A" Technical Specifications with the attached revised page. The revised page is identified by Amendment number and contains vertical lines indicating the area of change.
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TABLE 3.3-1 (Continued) l ACTION STATEMENTS l
l ACTION 2 - With the number of channels OPERABLE one less than the Total Number of l
' Channels, operation in the. applicable MODES may continue provided the inoperable channel is placed in the bypassed or tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
If the inoperable channel is bypassed for greater than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the desirability of maintaining this channel in the bypassed condition shall be reviewed at the next zegularly scheduled PSC meeting in accordance with the QA Manual Operations. The channel shall be i
returned to OPERABLE status prior to startup following the next COLD l
. SHUTDOWN.**
.With a channel process measurement circuit that affects multiple functional units inoperable or in test, bypass or trip all associated functional units as listed below.
i Process Measurement Circuit Functional Unit Bypassed 1.
Linear Power Linear Power Level - High (Subchannel or Linear)
Local Power Density - High DNBR - Low Log Power Level - High*
I 2.
Pressurizer Pressure - NR Pressurizer Pressure - High Local Power Density -High
.DNBR - Low 3.
Containment Pressure - NR Containment Pressure - High (RPS)
Containment Pressure - High (ESEAS)
Containment Pressure - High-High (ESEAS) 4.
Steam Generator 1 Pressure Steam Generator 1 Pressure - Low Steam Generator 1 AP (EEAS 1)
Steam Generator 2 AP (EEAS 2)
)
5.
Steam Generator 2 Pressure Steam Generator 2 Pressure - Low 1
Steam Generator 1 AP (EEAS 1) j Steam Generator 2 AP (EEAS 2)
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I 6.
Steam Generator 1 Level Steam Generator 1 Level - Low Steam Generator 1 Level - High Steam Generator 1 AP (EEAS 1) 7.
Steam Generator 2 Level Steam Generator 2 Level - Low Steam Generator 2 Level - High Steam Generator 2 AP (EEAS 2) 8.
Core Protection Calculator Local Power Density - High DNBR - Low Only for failure common to both linear power and log power.
- Channel "D" of Functional Units 2, 3a, 9, 10, and 14 is not required to be restored to OPERABLE status until the startup following the mid-cycle outage (2P99).
ARKANSAS.- UNIT 2 3/4 3-5 Amendment No, M,M9,M6,H4202 '
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