ML20137W412
| ML20137W412 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/16/1997 |
| From: | Kalman G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20137W420 | List: |
| References | |
| NPF-06-A-181 NUDOCS 9704180099 | |
| Download: ML20137W412 (7) | |
Text
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O nuou g
UNITED STATES g
j NUCLEAR REGULATORY COMMISSION o
2 WASHINGTON, D.C. 20056 4 001
'+9.....,o ENTERGY OPERATIONS. INC.
DOCKET NO. 50-368 j
ARKANSAS NUCLEAR ONE. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No.181 License No. NPF-6 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated December 19, 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Comission; 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 Comission's regulations; D.
The issuance of this license amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
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b 9704180099 970416 PDR ADOCK 05000368 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-6 is hereby amended to read as follows:
2.
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.181, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the j
Technical Specifications.
3.
The license amendment is effective as of its date of issuance.
FOR THE NUCLEA!! REGULATORY COMMISSION M" -
y George Kalman, 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: April 16,1997 1
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ATTACHMENT TO LICENSE AMENDMENT NO.181 FACILITY OPERATING LICENSE NO. NPF-6 1
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 page is also provided to maintain document completeness.
REMOVE PAGES INSERT PAGES XV XV 5-5 5-5 9
4 1
i INDEX DESIGN FEATURES SECTION PAGE 5.1 SITE t
Exclusion Axea..........................................
5-1 Low Population Zone.....................................
5-1 s
5.2 CONTAINMENT Con 11guration...........................................
5-1 Design Pressure and Temperature.........................
5-4 5.3 REACTOR CORE 4
Fuel Assemblies.........................................
5-4 Control Element Assemblies..............................
5-4 5.4 REACTOR COOLANT SYSTEM Design Pressure and Temperature.........................
5-4 5.5 METEOROLOGICAL TOWER LOCATION.................................
5-5 4
4 5.6 FUEL STORAGE Criticality-Spent Fuel..................................
5-5 Criticality-New Fuel....................................
5-5 I
Drainage................................................
5-5 Capacity................................................
5-5 5.7 COMPONENT CYCLIC OR T RANSI ENT LIMITS........................
5-5
-1 1
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ARKANSAS - UNIT 2 XV Amendment No. 40,l81
l INDEX k
ADMINISTRATIVE CONTROL SECTION PAGE 6.1 RESPONSIBILITY...............................................
6-1 6.2 ORGANIZATION 0ffsite.................................................
5-1 Facility Staff..........................................
6-1 6.3 UNIT STAFF QUAL!rICATIONS....................................
6-5 4
6.4 TRAINING.....................................................
4-5 6.5 DELETED ARKANSAS - UNIT 2 XVI Amendment No. 44,160 M ^25 Q 1
f.
DESIGN TEATURES 5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
5.6 FUEL STORAGE i
CRITICALITY - SPENT FUEL 5.6.1.1 The spent fuel racks are designed and shall be maintained so that the calculated effective multiplication factor is no greater than 0.95 (including all known uncertainties) when the pool is flooded with unborated water.
1 CRITICALITY - NEW FUEL 5.6.1.2 The new fuel storage racks are designed and shall be maintained with a nominal 25.0 inch center-to-center distance between new fuel assemblies such that K,gg wil,1 not exceed 0.98 when fuel having a maximum i
enrichment of 4.1 weight percent U-235 is in place and aqueous foam
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moderation is assumed and K,gg will not exceed 0.95 when the storage area is flooded with unbora*.ed water. The calculated K,gg includes a conservative allowance of 2.1% Ak/k for uncertainties.
DRAINAGE
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5.6.2 The spent fuel storage pool is designed and shall be maintainid to prevent inadvertent draining of the pool below eav.cion 399' 10b".
_ CAPACITY.
5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 988 fuel assemblies.
5.7 COMPONENT CYCLIC _,OR TRANSIENT LIMITS 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.
ARKANSAS - UNIT 2 5-5 Amendment No. 44,4,M,181
e TABLE 5.7-1 COMPONENT CYCLIC OR TRANSIENT LIMITS i
t a
y CYCLIC OR DESIGN CYCLE i
q C(MPONENT
- TRANSIENT LIMFT OR TRANSIENT _
~
Reactor Coolant System 500 system heatup and cooldoun Heatup cycle - T from < 200*F cycles at rates 1 100*F/hr.
to>545*F; coo 1838ncyciii-T,,, from > 545*F to 1 200*F.
500 pressurizer heatup and Heatup cycle - Pressurizer temperature cooldoun cycles at rates from 1 200*F to > 653*F; cooldoun 7
1 200*F/hr.
cycle - Pressurfr_er temperature from
> 653*F to < 200*F.
10 hydrostatic testing cycles.
RCS pressurized to 3110 psig with RCS temperature > 60*F above the j
most limiting components' NOTT value.
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200 leak testing cycles.
RCS pressured to 2250 psia with RCS temperature greater than minimum for l
t hydrostatic testing, but less than
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minimum RCS temperature for criticality.
1 400 reactor trip cycles.
Trip from 1001 of RATED THERMAL
(
POWER.
(
40 turbi'ne trip cycles with Turbine trip (total load rejection) delayed reactor trip.
from 1001 of RATED THERMAL POWER followed by resulting reactor trip.
3 200 seismic stress cycles.
Subjection to a seismic event equal to one half the design basis j
earthquake (DBE).
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