ML18095A609

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Proposed Tech Specs Re Fuel Assembly Enrichment Increase
ML18095A609
Person / Time
Site: Salem  PSEG icon.png
Issue date: 11/19/1990
From:
Public Service Enterprise Group
To:
Shared Package
ML18095A608 List:
References
NUDOCS 9011280352
Download: ML18095A609 (7)
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Text

,J ATTACHMENT 2 TECHNICAL SPECIFICATION PAGES WITH PEN AND INK CHANGES LICENSE CHANGE APPLICATION 90-14, NLR-N90197 FUEL ASSEMBLY ENRICHMENT INCREASE The following Technical Specifications are affected by this requested amendment:

Facility Operating License No. DPR-70 (Unit 1)

Technical Specification 5.3.1 5.6.1 5.6.3 Facility Operating License No. DPR-75 (Unit 2)

Technical Specification 5.3.1 5.6.1 5.6.3

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5-4 5-5 5-5 5-4 5-5 5-5

!:£SIGN. FEATURES

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DESIGN PRESSURE. AND TEMPERAT~RE 5 *.. 2~2.,The reactor containment building is designed and shall be maintained for a maximum internal pressure of 47 psig and an ai*r temperature of 271°F.

5.3 REACTOR CORE.

FUEL ASSEMB lIES 5.3.1 The reacto~ core shaii*contain 193 fuel assemblies with each fuel

~ssembly normally c~ntaining 264 fuel rods.clad wi~h Ziracloy-4 except that limited substituti*on of fuel.rods by filler rods consisting of Z-iracloy-4 or s*tair:iless steel *or by vacanci.es may be made if,Justified by.~- -cycle specific.

reload ana.lysis. *Each fuel rod shall have.a nominal active fuel length of '143.7 inches~ The initial-core loading shall have a maximum enrichment of 3.35 weight percent U-235.

Reload fuel shall be similar in h sical desi n t~ the core

  • loading and_ shall have*.a. ma icR'RJ.ent o 4.

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CONTROL ROD ASSEMBLiES*

5.3.2. The reactor core shall contain 53 full length and no part l~ngth control rod assemblies. The full length control rod assemblies shall contain_.a nom-ina.l 142 inches of absorber material. The nominal values of absorber material shall be 80 percent silver, 15 percent indium and 5 perce~~*cadmium. All controJ rods*

shall be clad with ~tainless steel tubing.

5.4 REACTOR COOLANT SYSTEM

~SIGN FEATURE. AND TEMPERATURE 5.4.1 The react6~ coolant system is.designed and shall be'maintain~d:

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SA LEM -

UN IT 1 5-4 Amendment No. 80

DESIGN FEATURES

a.

In accordance with the code requirements specified tn Section

  • 4.1 of the FSAR, with allowance for nonnal degradation pursuant to the applicable Surveillance Requirements,
b.

.. For". a ~ressure of 2485.p$ig~* and

c.

Fo~ a temper* tu re of 650~F.

  • except. for* the pressu.,.i zer" wh1 ch ts sao*F.

VOLUME 5.4.2 !he tota,.**water and* steam volume 9f the reactor coolant. system 1s**12,Sll *!, 100 CYbic feet at a ndmina1 Tavg of 576.7°F.

5.5.METEOROLOGICAL TOW~ LOCATION 5 o.5. 1, Th(I rr&t..Q~f'.11 ~S! i C:~ 1 t.G: :e1' ~ ~-,t_ 1'1 t't~ 1 CCZ1 ttti ~ ~ :i: h0~1 ~n Fig1.1re 5. lcl e

5. 6 FUEL STORAGE
  • d spent fuei
  • era*ge racks esigned Ind sh th a* nominal inch center-

-center distanc etween new el ~ss lies and an inal 10.5 in center-to-cente istance between spent uel assemb1i

  • placed in th storage racks to nsu,-e a k ff equivale to 0.95 witn t. storage pool i11ed with unbar ed water.

TRe k 0795 includ a conservati allowance of 2.

10

~k/k for uncertain DRAINAGE 5.6.2 The spent fuel storage pool 1s designed and shall be maintained to prevent inadvertent draining of the pool be1'ow elevation 124'8".

CAPACITY assemblies.

SALEM - UNIT 1 5.5 Amendment No. 3 3, s s

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5.6.l

a.
b.
c.
d.

The new and spent fuel storage racks are designed and shall be maintained with:

A keff equivalent to less than or equal to 0.95 with the storage rack filled with unborated water. The keff includes an allowance for uncertainties as described in section 9.1.2.1 of the UFSAR.

A nominal 10.5 inch center-to-center distance between fuel assemblies placed in the spent fuel storage racks.

A nominal 21.0 inch center-to-center distance between fuel assemblies placed in the new fuel storage racks.

A maximum reference fuel assembly kinf less than or equal to 1.453 in the core geometry at 68°F with no soluble boron.

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t:ES IGN FEATWRES

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DESIGN PRESSURE AND TEMPERATURE 5.2.2 The reactor containmen~ building is designed.. and shall be maintained for a maximum internal pressure of 4~psig and an air temp~rature of 271°F~

5.3 *REACTOR CORE FUEL ASSEMBLIES 5.3.1 The react6r core shall contain 193 fuel assemblies with each fuel assembly normally containing 264 fuel rods clad with Ziracloy-4 except that limited substitution of fuelrods by filler rods co*nsisting*of Ziracloy-4 or st,ainless steel or by vacanc1es may be made if just.H1ed by a cycle specific reload analysis.

Each, fuel rod shall have a nominal active fuel lehgth of 143.7 inches.

The {nifiaf core loadin[ shall have a maximum enrichment of 3.55 weight

  • percent~U-2*35. Reldad fu'e, sha*11 be similar in h sical desi n loading ana shall hav~. a m hmen1'.gf "'\\_.05~ei. t ~rrot °tl-2 CONTROL ROD ASSEMB.LIES..

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5.3.2 The reactor core shall contain 53 full length and no part.length control rod assemblies.

The full.length 'control rod assemblies shall contai*n a nominal 142 inches of absorber material.

The nominal values of absorber material shall

All control rods.

  • shall* ~e clad with stainless steel tubing.
  • 5.4 REACT°bR COG LANT SYSTEM.

t:ESIGN FEATURE AND TEMPERATURE 5.4.i The reactor. coolant system is designed and shall be maintained:

a.

In accordance with the *code requirement specified in Section 4.1 of the FSAR, with a11owance for norma1 degradation pursuant to the applicable Surveillance Requirem~nts,

~. For* a pressure of 2485 pstg, and

c.

For a temperature of 650°F-*, except for the pressurizer wh'i ch* is 680°F.

W~E 5.4.2 The total water and steam volume of the reactor coolant syste~ is 12,811..!,100 cubic f;eet at ~.. nominal Tavg of 581.0°F.

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UN IT 2 5-4

,Amendment rn.

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DESIGN FEATURES 5.5 METEOROLOGiCAL TOWER LOCATION

5. 5. 1
  • Th!! meteorological tower -stial 1 be located as shown on Figure 5. 1-1.

5.6 FUEL STORAGE

b.

DRAINAGE

5. 6. 2 The spent fue 1 storag~ poo 1 is dis i gned and
  • sha 11 be ma i nt*a ined. to prevent inadvertent _drainM*g of.the poQ.l below elevation 124 18 11 CAPACITY 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.7. 1 The components identified in Table 5.7-1 are designed.and shall be maintained within the cyclic or transient Umits of Table '5. 7-1.

SALEM - UNIT *2 5-5 Amendment No. 22 I'

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5.6.1

a.
b.
c.
d.

The new and spent fuel storage racks are designed and shall be maintained with:

A keff equivalent to less than or equal to 0.95 with the storage rack filled with unborated water. The keff includes an allowance for uncertainties as described in section 9.1.2.1 of the UFSAR.

A nominal 10.5 inch center-to-center distance between fuel assemblies placed in the spent fuel storage racks.

A nominal 21.0 inch center-to-center distance between fuel assemblies placed in the new fuel storage racks.

A maximum reference fuel assembly kinf less than or equal to 1.453 in the core geometry at 68°F with no soluble boron.

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