ML17194A284
| ML17194A284 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 10/29/1981 |
| From: | Novak T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17194A283 | List: |
| References | |
| NUDOCS 8111300047 | |
| Download: ML17194A284 (5) | |
Text
4* *.
UNITED STAT.ES NUCLEAR REGULATORY COMMISSION
. WASHINGTON; D. C. 20555 COMMONWEALTH EDISON COMPANY
.. _ DOCKET NO. 50-249 DRESDEN STATION UNIT NO. 3 *
. AMENDMENT "TO FACILITY OPERATING LICENSE Amen'drrient No;* 56 License.No. DPR-25
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by tne Commonwealth Edison Company.
(the licensee) dated May 11, 1978; and the licensee 1s request *;
- dated August 10, 1981, as supplement~d and supported by the information t~ans~itted by letters dated January 12 and 24~ 1979, May 30, 1979, Jun~ 12, 1979, August 17~ 1979, October 19 and 29, 1979~ December 2, 1980, January 29, 1981, and June 8, 1981, comply with-the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission 1s rules and regulations set forth in lD 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-fhi~ 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 1s 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 publi~; and
- f. The issuance.of this amend~ent is in accordance with 10 CFR. Part 51 of the Commission 1s regulations and all applicable requirements have been satisfied.
- 9* 2.
Accordingly, pursuant to the Atomic Safety and Licensing Board's "Partial Initial 'Decision Modifying Operating License to Permit Installation of Five High-Density Spent Fuel Storage Racks at Dresden Unit 3 11
, dated September 24, 1981, Facility Operating License No. DPR-25 is hereby amended* as follows:.
A n~w P~ragraph.3.M ii added to read:
Ma Spent Fu~l Strirage Racks
- 1. The licensee is authorized to install and use five high-density fuel storage racks in the spent fuel storage pool at Dresden Station Unit 3.
~
- 2.
Fuel stored* in the spent fuel pool shall have a U-235 loading less than or equal to 14.8 grams per axial centimeter.
- 3.
No loads heavier than the weight of a single spent fuel assembly and handling tool shall be carried over fuel stored in the spent fuel pool.
- 4.
The licensee shall update the Dresden Station Unit 3 FSAR within 8 months from the effective date of this amendment to reflect the fella.wing commitment~:
- a.
A corrosion surveillance program for the racks to insure 'that any loss of reutron absorber material and/or swe 11 i ng of the star.age t~bes. is detected..
- b. l!J. situ-neutron attenuation tests to verify that tubes and racks contain a sufficient number of Baral plates such that K-effective will not be greater than 0.95 when the spent fuel is in place.
- c.
If one boral plate is detected missing, the associated tube will be blocked to prohibit insertion of a fuel assembly.
If more than one missing boral plate is detected per pool, the* licensee will remove the storage rack or racks containing any.additional missing boral plates from the pool.
Such storage racks wi 11 not be rep 1 aced. in the poo 1 unti 1 a specific criticality analysis covering the pro-posed corrective action has been submitt~d to and approved by the NRC.
tj.
Before a~y storage rack is placed in the Dresden pools~
the licensee will check each storage location with a plug gauge to confirm that the minimum dimension between the lead-in clips at the top of each storage location is at least 5.758 inches.
If necessary, the l~~ensee will gr'l"nd down the.storage clips to ensµre this dimension is achieved.
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-- 3.
-e
- -- Chanqc::s to-: the. Technical SpecifTC:ations as lridicateo in the attachment to. tn i <; 1 i C:cns-e ani-:ndment ~and Paragraph 3.B is.hereby amended to read
- as follows:_*
B.
- Technical Specificaticiris
- .;_--~ Jhe Technica 0i Specifications.;c_ontained :in;APP.. ~~dix A, as revised
- -* __ : through Amendment Na:* 56, are hereby 'incorporated in the license.
- The 1 i cens!=e sha 11 operate the* f aci 1 ity* in a{cordance with the
- ~
- *:*Technical Specificafions.
~:
-~---
- c;.
~
This:'Jicense ame-~dment is effectjve as o(the-ci_ate:of its issuance.
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- .~.
~:FOR THE NUCLEAR RE-GULATORY COMMISSION * -,
......... -.~ - ::.
Attachment:
- Changes to the Technica~
Spec ifi cations
~~~...
-~--~.~a~~-
"-:Thomas M~.Nova*k~~ A~sistant for Operating Reactors --
- Division of ~ice~sJrig
.~
Date* of Issuance: Octob*er 29, 1981 Director
e*
ATTACHMENT lo LICENSE AMENDMENT NO. 56 FACILITY OPERATING LICENSE NO. DPR-25
. DOCKET.No. 50-249
- Revise the Appendix 11A 11 Technical SpecifiCations by replacing the existing Page 157 with the attached Page 157.
1_
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5.0 5.1 5.2 5.3 DESIGN FEATURES Site Dresden U~lt 3 ta lo~ii.tcd at tho :Ore~dc~1 l'{4C;,lear Power-.Station which conalSta of n tract of ln.nd ot * ',
approximately 953 acres located in the nqrtheaat.
quarter of the Morris 15-minute qundro.n'glo (as de.signated by the United States Geological Survey),
Goose Lake Township, Grudy County, llllnole..
Tho tract ls situated in PQrtlona of SeoUop~. 25, 26,.
27,* 34, 35, and 36 of ToVltlship 34 North, 1*!lange 8 ***
East of the Third Principal Meridian~
Reactor A. The core shall consist *of not more than 724 fuel aaeemblles.
B. The reactor core a hall contain 177 cruciform-
.
- shaped control rods. The control material shall be boron carbide powder (B4C) compacted to approximately 70% of theoretical density.
Reactor Vessel The reactor vceecl shnll be as de:;~ribcd in Table 4.1.1 of the SAR.' The applicable design codes shall be as described in Tnblc -1, l, l of the SAR,' * *
/
- 5. 4 contahinu~nt:
- *A. The principal design parameters and app1 lcablo design code~ for u~e primary containment shnll
- ** *.be~ glyen ln 'filhle.~,2.1 of tho SAR *
=U ~.. The aeoondacy contatnment* shall be as de-
- '
- scribed. in Section 6. 3. 2 of the SAR and tho applicable. codes shall be as described in section 12.1,l.3 of the BAR. *.. *.
. *a~
- Ponetrations to the p~imary containment and*
'. plplrig passing through suoh penetrations shall
.. :he designed in 41ooordance with.standarda*set,
.. '. forth ln Seciton 6 ~ 2. 2 of the SAR.
- 5. 5
.Fuel storage :.
i.**
. :'r1
.,.i,. *The new fuel.storage.facility shallbe such that **.. *
- 'the Kett :dry ls less than 0.9.0,and flooded is*.
less than 0.96.
B.. The ~ff of tile spent fuel storage pool shall be lees than or equal.to 0.-95 *
.. ** 6. 6., Seismic Design *.
I.
Tho reactor building and all cont9.ined engineered
- safegards are designed for the maximum credible earthquake ground motion.with an acceleration of 20 per cent of gravity. Dynamic analysis was used
- to determine the earthquake acceleration, nppllcnble *
- to the various elevations in the reactor building.
. *\\
- I>
[.*
Change Nq~ J~,
Amendment No. 56
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157
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