ML20210S964

From kanterella
Jump to navigation Jump to search
Amends 179 & 183 to Licenses DPR-24 & DPR-27,respectively,to Revise TS 15.5.4, Fuel Storage, to Increase Fuel Assembly Enrichment Limits to 5.0 Weight Percent
ML20210S964
Person / Time
Site: Point Beach  
Issue date: 09/04/1997
From: Gundrum L
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20210S969 List:
References
NUDOCS 9709120220
Download: ML20210S964 (7)


Text

m as4 9

k UNITED STATES pe s

P; NUCLEAR RECULATORY CIMMISSIEN WASHINGTON, 0.c. seeeHoot WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50 266 POINT BEACH NUCLEAR PLANT. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE l

i Amendment No.179 License No. DPR 24 l

1.

The Nuclear Regulatory Commission (the Commission) has found that:

I A.

The application for amendment by Wisconsin Electric Power Company (the licensee) dated January 24,1997, as supplemented on May 15 and August 5, 1997, 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 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.

9709120220 970904 PDR ADOCK 05000266 P

PDR

2 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR 24 is hereby amended to read as follows:

B.

Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.179, are hereby incorporated in the license. The licensee shall operate the facility in accordance with Technical Specifications.

3.

This license amendment is effective immediately upon issuance. The Technical Specifications are to be implemented within 45 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION d

M Linda L. Gundrum, Project Manager Project Directorate lil 1 Division of Reactor Projects lil/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance: September 4, 1997 I

w w

y

-,-w--=+

m-+-w--, -

--w-

<w--

w y

,r r,w---,,-y-g-=,-y,-s-u

+,,wu-mem---

+ N *-

me:

p*-

UNITED STATES g

}

NUCLEAR RESULATCRY CIMM18812N wAswiwovow, o.c. sneewooi WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-301 POINT BEACH NUCLEAR PLANT. UNIT No. 2 AMENDMENT TO FACILIW OPERATING LICENSE

)

)

l Amendment No.183 License No. DPR 27 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Wisconsin Electric Power Company (the licensee) dated January 24,1997, as supplemented on May 15 and August 5, 1997, 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; r

B.

The facility will operate in conformity with the application, the provisions of the l

I Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this I

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 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.

a

4 2-2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8 of Facility operating License No. DPR 27 is hereby amended to road as follows:

B.

Technical Specificationg The Technical Specifications contained in Appendims A and B, as revised through Amendment No.183, are hereby incorporated in the license. The licensee shall operate the facility in accordance with Technical Specifications.

3.

This license amendment is effective immediately upon issuance. The Technical Specifications are to be implemented within 45 days from the date of issuance.

L FOR THE NUCLEAR REGULATORY COMMISSION I

4,M. h -

Linda L. Gundrum, Project Manager Project Directorate Ill.1 Division of Reactor Projects lilllV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Speci6 cations Date of issuance: September 4,1997

____ _ _ ~_

~

u

4 ATTACHMENT TO LICENSE AMENDMENT NOS179 AND 183 IQ E6CILITY OPERATING LICENSE NOS. DPR 24 AND DPR 27 DOCKET NOS. 50 266 AND 50 301 Revise Appendix A Technical SpecNications by removing the pages identified below and inserting the enclosed pages The revised pages are identified by amendment number and contain vertical lines indicating the area of change, REMOVE INSERT 15.5.4 1 15.5.4 1 15.5.4 2

- : ~ ~~ ::~~ ~ ~. - - -- -

i i

)

- 15.5.4 FUEL STOMGE l

f Anolicability Applies to the capacity and storage arrays of new and spent fuel.

i OhiacHvo 1

i j

To define those aspects of fuel storage relating to prevention of criticality in fuel storage areas.

t Specification i

1.

The new fuel storage and spent fuel pool structures are designed to withstand the j

anticipated earthquake loadings as Class I structures. The spent fuel pool has a i

stainless steel liner to ensure against loss of water.

l 2.

The new and spent fuel storage rocks are designed so that it is impossible to store i

assemblies in other than the prescribed storage locations. The fuelis stored vertically in j

an array with sufficient conter-to-conter distance between assemblies to assure l

[

K, < 0.g5 with the storage pool filled with unborated water and with the fuel loading in the assemblies limited to 5.0 w/o U 235, with or without axial blanket loadings. Each a

assembly with a fuel loading greater than 4.6 w/o U 235 must contain integral Fuel p

Bumable Absorber (IFBA) rods in accordance with Figure 15.5.41 or have a reference i

infinite multiplication factor, K., less than or equal to 1.4g364, which includes a 1% AK i

1

- reactivity bias. An inspection area shall allow rotation of fuel assemblies for visual I

inspection, but'shall not be used for storage.

3.

The spent fuel storage pool shall be filled with borated water at a concentration of at

[

least 1800 ppm boron whenever there are spent fuel assemblies in the storage pool.

e Except for the two storage locations adjacent to the designated slot for the spent fuel i

4.

j storage rock neutron absorbing material surveillance specimen irradiation, spent fuel l

assembly storage locations immediately adjacent to the spent fuel pool perimeter or j

divider walls shall not be occupied by fuel assemblies which have been subcitical for

[

j less than one year.

i r

I l

- Unit 1 - Amendment 35,77,84,444,436, 179 Unit 2 - Amendment 44,44,99,430,430, 183 15.5.4 1 et

.,g-*-

sow tr-. w w, y

as n.

,-e,-

we,,,

,e,rww.--w

=r.wr

.i,--1

--s.e-ew am

  • a-w-em-v r-e--o w +e -e -e--m e a-er
  1. -~

ee--

Figure 15.5.41 Fuel Assembly IFBA Requirements 16 1.0X IFBA Loadnq 1.5X IFBA Load 2.0X IFBA Load 12

/

/

ACCE PTABL E

$.a

/

f g

4

/

/

UNACCEPTABLE f.......

/....~

o 4.60 4.70 4.80 4.90 5.00 ass Enrichment (wlo) u Note: 1.0X,1.5X, and 2.0X IFBA rods have nominal poison material loadings of 1.67,2.50, and 3.34 milligrams B-10 per inch, respectively.

Unit 1 - Amendment 179 Unit 2 - Amendment 183 15.5.4-2

'