ML20095G770

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Amend 164 to License DPR-50,revising TMI-1 TS to Reflect Planned Reracking of Spent Fuel Pool a to Allow Addl Storage Capacity
ML20095G770
Person / Time
Site: Crane Constellation icon.png
Issue date: 04/27/1992
From: Stolz J
Office of Nuclear Reactor Regulation
To:
Metropolitan Edison Co, Jersey Central Power & Light Co, Pennsylvania Electric Co, GPU Nuclear Corp
Shared Package
ML20095G775 List:
References
DPR-50-A-164 NUDOCS 9204290129
Download: ML20095G770 (7)
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- UNITED STATES g

-NUCLEAR REGULATORY COMMISSION

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METROPOLITAN EDISON COMPANY JERSEY CENTRAL' POWER &-LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY GPU NUCLEAR CORPORATLQR DOCKET NO. 50-289 THREE MILE ISLAND NUCLEAR STATION. UNIT NO.j AMENDMENT TO FACILITY OPERATING LICENSE Amendment'No. 164 License No. DPR 1 -,

The Nuclear Pegulatory Comission (the Commission) has found that:

-A.

The application for amendment _by GPU Nuclear Corporation, et al.

(the licensee) dated November 14, 1990, as supplemented June 6, June 14, September 18, November 17, and December-12, 1991, and February 13, 1992,-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 Comission; C..

There is reasonable assurance _(1) 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' enth the Commission's regulations;

- D.

The' issuance of this amendment will not be' inimical to the common.

defense-and.*ecurity 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.

9204290129.920427 PDR -ADOCK 05000209 P.

PDR

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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.

DPR-50 is hereby, amended _to read as follows:--

_(2) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.164,- are hereby incorporated _in the license. GPU Nuclear Corporation shall operite the._facili_ty in _accordance with the 1 Technical Specifications.

3.

This license amendment'is effective as of its date of issuance, to be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY' COMMISSION f ? fb t($4A John F. Stolz, Director-Project Directorate I_4-Division of Reactor Projects'- I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:-

April 27, 1992 x

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4 ATTACHMENT TO LICENSE AMENOMENT N0.164 FACILITY OPEllATING LICENSE NO. DPR-50 DOCKET NO. 50-289 Replace 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.

Egmove Insert viii viii 5-6 5-6 5-7 5-7 5-7a

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l LIST 10F FIGURES a

Figure Title 3.5-2K-

-thru

. DELETED 3.5-2L.

.3.5-2M LOCA Limited Maximum Allowable Linear Heat Rate

-3!5-1 Incore Instrumentation Specification Axial Imbalance Indication, TMI-1 3.5.Incore Instrumentation Specification Radial Flux Tilt Indication,.TMI-1 3.5-3

.Incore Instrumentation Specification 13.11-1 Transfer Path to and from Cask Leading Pit 4.17-1

-Snubber Functional Test - Sample Plan 2 5-1 Extended Plot Plan TM1 5-2 Site _ Topography 5 Mile Radius 1 3 Locations of Gaseous Effluent Release Points and Liquid Effluent Outfalls L

. 54 Relationship Between Initial Enrichment and Acceptable Fuel Burnup (Spent Fuel Pool A - Region II)

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. Amendment Nos. 72, 77, 126, 139, 142, 149, 150, 156, 164 l

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5.4 ~

NEW AND SPENT FUEL STORAGE FAC1L1T2ES

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w Applicability-- - -

-Applies to storage-faci _11 ties.for new and spent fue1~ assemblies.

Objective i

To assura that both new and spent fuel assemblies will be stored in such a manner that an inadvertent criticality could not o'ccur.

Specification

-5.4.11 NEW FUEL ST0AAGE' New fuel will normally be stored:in the new fuel storage a;

v'ault or spent fuel pools.- The fuel assemblies are stored in racks in parallel rows, having a nominal center to center distance of 21-1/8 inches.in'both directions for the new fuel storage vault. The fuel assemblies are

-stored in-racks in parallel-rows, having a nominal center to center distance of 11.1 inches in both directions for

-the. Region 1-racks and 9.20 inches in-both directions for

-the Region 11 racks-for-the Spent Fuel-Pool "A.".

The fuel' assemblies areistered_in racks in parallel rows l having a nominal: center to center _ distance of-13-5/8 inches in both

' directions for the Spent Fuel Pool "B". -This spacing;is sufficient to maintain a K effective of.less-than.95'-

based:en-fuel assetnblies with an enrichment of 4.3 weight

' percent US** for-the _new fuel storage -vault and Spent -

Fuel Pool B".

The spacing is sufficient'to maintain a 1 effective of-less than.95 based on fuel assemblie with an enrichment of 4.6 weight percent U*** for Region 1 of the-Spent Fuel-Pool."A". :When fuel _is_being stored in the new fuel' storage vault, twelve (12) _ storage locations (aligned in two rows of six_-locations each; transverse row numbers:four'and-eight)-must be left-vacant of fissile or-moderating; material-.to provide sufficient neutron leakage to satisfy the NRC maximum _ allowable reactivity value under the optimum low moderator density condition. When:

fuel is:being moved in-or over the Spent Fuel Storage Pool

"A'? and fuel is being stored-in the pool, a boron concentration of at least 600 ppmb must be maintained to.

--ensure meeting tha-NRC maximum allowable reactivity value-

-under the postulated accident ~ condition:of a misplaced fuel assembly.

.b. --Deleted,

c. -New fuel may also be stored-in shipping containers.

5-6 Amendment No. 138, 164 j

  • 5.4.2 SPENT FUEL STORAGE (Reference 1) 9-a.

Irradiated fuel assemblies will-be stored, prior to offsite. shipment, in the stainless steel-lined spent fuel

pools, which are located in the fuel handling building.

b.

Whenever there is fuel in the poc1 except for initial fuel loading, the spent fuel pool is filled with water borated to the concentration used in the reactor cavity and fuel transfer canal, c.

Deleted.

d; The fuel assembly storage racks provided and the number of fuel elements each will store are listed by location below:

Spent Fuel Pool A Spent Fuel Pool B Dry New Fuel North End of Fuel South End of Fuel Storage Area Handling Building Handling Building Fuel Handling Building Fuel Assys 846 **

406 ***

-66****

Cores-4.78 2.8 0.37 NOTES: ** Includes three spaces for accommodating failed fuel containers.

An additional 648 storage locations can be installed to provide a total of 1494 locations, or 8.44 cores.

      • Spent Fuel Pool B contains spent fuel storage racks with a center-to-center spacing of 13 5/8 inches to increase the storage capacity of the pool.
        • -Ir.:1udes twelve spaces which are required to be vacant of fissile or moderating material so that there is sufficient neutron leakage, All of the fuel assembly storage racks provided are e.

designed to Seismic Class 1 criteria to the accelerations indicated below:

Fuel Handling' Building Fuel Handling

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Dry New Fuel Storage Area Building Spent And Spent Fuel pool A Fuel pool B Hori:.

0.38 g-Vertical 0.25 g

  • The "B" pool fuel storage racks are designed using the floor response spectra of the Fuel Handling Building, i

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Fuel in the storage pool shall have a U-235 loading equal to or less than 57.8 grams of U-235 per axial centimeter of fuel p

assembly.

g.

When spent fuel assemblies are stored in Region 11 storage racks of the Spent Fuel Pool "A", the combination of initial i

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enrichment and cumulative burnup for spent fuel assemblies shall be within the acceptable area of Figure 5-4 REFERENCES (1) UFSAR, Section 9.7

" Fuel Handling System" l

5-7 Amendment No M, (16, 157, 164 SEP 2 51990

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ts to a.s As As s.s INmAL ENIOCHM, WDs U-235 Figure 5-4 Relationship between Initial Enrichment and Acceptable Fuel Burnup (Spent Fuel Fool A - Region II) 5-7a

.-Amendment No. 164'

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