ML20210T000
| ML20210T000 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 08/09/1999 |
| From: | Stephen Dembek NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20210T005 | List: |
| References | |
| NUDOCS 9908180254 | |
| Download: ML20210T000 (7) | |
Text
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j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. SoseHoot
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i WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.126 License No. NPF-42 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Wolf Creek Generating Station (the facility) i Facility Operating License No. NPF-42 filed by the Wolf Creek Nuclear Operating Corporation (the Corporation), dated June 10,1999, complies with the standerds 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; 1
B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activlies afhorized by this amendment can be conducted without endangering the hea th and safaty 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 satiswd.
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i 9908190254 990009 PDR ADOCK 05000482 p
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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. NPF-42 is hereby amended to read as follows:
2.
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 126, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the i
license. The Corporation shall operate the facility in accordance with the T'echnical Specifications and the Environmental Protection Plan.
I 3.
The license amendment is effective as of its date of issuance and shall be implemented within 60 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION S ep en Dem k, Chief, Section 2 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: August 9, 1999
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ATTACHMENT TO LICENSE AMENDMENT NO. 126 FACILITY OPERATING LICENSE NO. NPF-42 DOCKET NO. 50-482 Revise the current Appendix A Technical Specifications (CTS), including the issued but not yet implemented improved Technical Specifications (ITS), by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by amendment number and contain marginallines indicating the areas of change. The corresponding overleaf pages are also provided for the CTS and ITS to maintain document completeness.
REMOVE INSERT CTS 3/4 3-26 CTS 3/4 3-26 ITS 3.3-36 ITS 3.3-36 I
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ESFAS InStrumentCtion 3
3.3.2 Table 3.3.2-1 (page 4 of 5)
Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE I
FUNCTION CONDrTIONS CHANNELS CONDITIONS REQUIREMENTS VALUE (a) j l
6.
Auxiliary Feedweder s.
Manualinibsten 1,2,3 1 por pump O
SR 3.3.2.8 NA b.
Automatic Actuation 1,2,3 2 trains G
SR 3.3.2.2 NA Logic and Actuation SR 3.3.2.4 s
i Relays (Solid State SR 3.3.2.6 Protection System) c.
Automatic Actuation 1.2.3 2 trains N
SR 3.3.2.3 NA Logic and Actuaten Relays (Balance of Plant ESFAS) d.
SG Water Level Low.
1,2,3 4 per SG D
SR 3.3.2.1 2 22.3% of Low SR 3.3.2.5 Narrow Range SR 3.3.2.g instrument Span j
SR 3.3.2.10 1
e.
Safety injection Refer to Function 1 (Safety injection) for all initiation funchons and requirements.
I f.
Loss of Offsite Power 1,2,3 2 trains P
SR 3.3.2.7 NA l
g.
Trip of au Main '
1 2 per pump J
SR 3.3.2.8 NA
{
Feedwater Pumps
~
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Auxiliary Feedwater 1,2,3 3
M SR 3.3.2.1 2 20.53 pois i
Pump Sucten SR 3.3.2.g Transfer on Suction -
SR 3.3.2.12 Pressure Low l
I (continued)
(a) The ANowabis Value defines the Lnnoung Safety System Sethng See the Bases br the Trip Sotpoints.
I Wolf Creek-Unit 1 3.3-35 Amendment No.123
~
ESPAS inStrumentaten j
3.3.2 Table 3.3.2-1 (page 5 of 5)
Engineered Safety Feature Actuaton System instrumentation I
I APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS - CHANNELS CONDITIONS REQUIREMENTS VALUE(a) 7.
Automatic Switchover to
- Containment Sump a.
Automatic Actuation 1,2,3,4 2 trains C
SR 3.3.2.2 NA Logic and Actuation SR 3.3.2.4 Reisys SR 3.3.2.6 SR 3.3.2.13 b.
Refueling Water 1,2,3,4 4
K SR 3.3.2.1 2 35.5% of l
Storage Tank SR 3.3.2.5 instrument span (RWST) Level Low SR 3.3.2.9 Low SR 3.3.2.10 Coincident with Safety Refer to Function 1 (Safety injecton) for all initetion functions and roovirements.
Injection 8.'
ESFAS Interlocks s.
Reactor Tnp, P 4 1,2,3 2 per train, F
SR 3.3.2.11 NA 2 trains
- b.. Pressurizer Pressure, 1,2,3 3
L SR 3.3.2.5 51979 psig P-11 SR 3.3.2.9 a
(a) The Alloweble Value defines the Limiting Safety System Settings. See the Bases for the Trip Setpoints.
e Wolf Creek-Unit 1 3.3-36 Amendment NO.433,126
.