ML18100A935

From kanterella
Jump to navigation Jump to search
Proposed Tech Specs Revise Sections 5.3 & 5.6 of TS to Allow Use of Westinghouse Vantage+ Fuel W/Zirlo Cladding
ML18100A935
Person / Time
Site: Salem  PSEG icon.png
Issue date: 03/04/1994
From:
Public Service Enterprise Group
To:
Shared Package
ML18100A934 List:
References
NUDOCS 9403140272
Download: ML18100A935 (7)
v • d • e


Text

ATTACHMENT 2 r---

DESIGN FEATURES e

~=~=~===================================================================

  • DESIGN PBESSYRE AND TEMPERATURE 5.2.2 Th* reactor containment building is de*igned and shall be maintained for a maximum internal pre*sure of 47 paig and an air temperature of 271°F.

5.3 BEACTOR COBE Ref /a.ce*

eviFh

Z:::fl£erf CQNTRQL ROQ ASSEM8LIES 5.3.2 The reactor core *hall contain 53 full lenqth and no part lenqth control rod a**embli*** The full lenqth control rod a**embli** shall contain a nominal 142 inch** of ab*orber matarial. The nominal value* of abaorber material *hall be 80 percent ailver, 15 percent indium and S percent cadmium.

All control rod* *hall be clad with stainle** *t**l tubing.

5.4 UACTQR COOLANT SYSTEM DESIGN FEA'l'tJRI AND TEMfEBATURE S.4.1 Th* reactor coolant system i* de*igned and *hall be maintained:

SALEM - UNIT 1 5-4 Amendment No. 128

Insert 1 5.3.1 The reactor shall contain at least 193 fuel assemblies.

Each assembly shall consist of a matrix of zirconium alloy clad fuel rods with an initial composition of natural or slightly enriched uranium dioxide as fuel material. Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff approved codes and methods and shown by tests_ or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions.

e e DESIGN FEATURES

=-------=*======~~==~----------------*===**================

a. In accordance with the code requirements specified in Section 4.1 of the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirement&,
b. For a prea*ur* of 2485 psig, and
c. For a temperature of 650°F, except for the pressurizer which is 680°F.

VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is 12 1 811 +/- 100 cubic feet at a nominal Tavg of 576.7°F.

5.5 HEIEORQLQGICAL TOWiR LQCATION S.S.l The meteorological tower uhall be located a* *hewn on Figure S.l-l.

5.6 FYEL STORAGE CRITICALITY 5.6.1 Th* new and *pent fuel *torag* rack* are d**igned and *hall be maintained with:

a. A Keff equivalent to l*** than or equal to 0.95 with the storage --

rack filled with unborated water. Thi* value of keff includes a con*ervative allowance of:

1. 2.2, delta k/k uncertainty for all *tandardAand V5H fuel

>Va.nfa.~e + a**emblie*, and

2. An additional 0.7, delta k/k uncertainty for *tandard~and VSH fuel a**embli** containing Integral Fuel Burnable Absorber (IFBA) pin*.
b. A nominal 10.5 inch center-to-center di*tance between fuel a**embli** placed in the spent fuel *torage racX..
c. A nominal 21.0 inch center-to-center di*tance between fuel a**embli** placed in the new fuel *torage rack*.
d. Standard~r Vantage SH fuel a**embli** with maximum enrichment of 4.55 w/o 0235 and a Kint l*** than or equal to 1.453 in th* core geometry at 68°F with no aolubl* boron.

DMIUAGI 5.6.2 Th* *pent fuel *torag* pool i* de*igned and *hall be maintained to prevent inadvertent draining of the pool below elevation 124 8*. 1 SAI.ZH - UNIT 1 5-5 Amendment No. 128

DESIGN FEATURES QESIGN PJ\ISSURJ!j AND TEMPER,ATURE 5.2.2 Th* reactor containment building ia designed and ahall be maintained for a maximum internal preaaure of 47 paiq and an air temperature of 271°F.

5.3 J!EACTOR CORE FUEL ASSEMBLIES Repla.ce evi+~

Cr\JSer+- I *tainl*** *t**l or by reload analy*i*. E 143. 7 i.ne.J~r:-

CQNTRQL RQD ASSEHBLIES S.J.2 The reactor core *hall contain 53 full length and no part length control rod a**embli*** Th* full length control rod a**embli** *hall contain a nominal 142 inch** of ab*orber material. The nominal value* of ab*orber material *hall be 80 percent *ilver, 15 percent indium and 5 percent cadmium.

All control rod* *hall b* clad with *tainl*** *t**l tubing.

5.4 UAC'l'QR COOLANT SYSTEM DESIGH llATtJRI AND TIKPEBATtlJU!

5.4.1 Th* reactor coolant *y*tem i* d**igned and *hall be maintained:

a. In accordance with the code requirement *pecified in Section 4.l of th* FSAR, with allowance for normal degradation pur*uant to the applicable Surveillance Requirement*,
b. Per a pr***ure of 2485 p*ig, and
c. ror a temperature of 650°r, except for the pr***urizer which i* 6ao*r.

VOLtlMI 5.4.2 Th* total water and *team volume of the reactor coolant sy*tem is 12,811 :t 100 cubic feet at a nominal T of 581.0°P.

avg SALEM - UNIT 2 5-4 Amendment No.107

Insert 1 5.3.1 The reactor shall contain at least 193 fuel assemblies.

Each assembly shall consist of a matrix of zirconium alloy clad fuel rods with an initial composition of natural or slightly enriched uranium dioxide as fuel material. Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff approved codes and methods and shown by tests or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions.

r-DESIGN FEATURES e e

*-*************************-~-------~---***---~---*-****=~==============

j.5 Ml'l'IQRQLQGICAL TOWER LOC~TION 5.5.l Th* meteorological tower shall be located a* *hewn on Figure s.1-1.

5.6 rtl!jL STQRMjl CRITICALITY 5.6.l Th* new and spent fuel *torage rack* are de*igned and shall be maintained with:

a. A Keff equivalent to l*** than or equal to 0.95 with th* storage rack filled with unborated water. Thi* value of keff include* a con*ervativ* allowance of:
1. 2.2\ delta k/k uncertainty for all *tandar~and V5H fuel
      • embli**, and J Va.n+a.~e + 2. An additional 0.7, delta k/k uncertainty for *tandard~and VSH

. fuel a**emblie* containing Integral Fuel Burnable AD*orb*r (IFBA) pin*.

b.* A nominal 1o:s inch center-to-center di*tance between fuel a**embli** placed in th* *pent fuel *torage raclca.

c. A nominal 21.0 inch center-to-center di*tance between fuel a**embli** placed in the new fuel *torage raclca. --
d. Standard'ltor Vantage SH fuel ***embli** with maximum enrichment of 4.55 w/o 0235 and a Kinf le** than or equal to 1.453 in the core geometry at &a*p with no *olubl* boron.

DBAilfAGI 5.6.2 The *pent fuel *torage pool i* de*igned and *hall be maintained to prevent inadvertent draining of the pool below elevation 124 8*. 1 CpACITX 5.6.l lfb8 mpent fuel *toraqe pool i* de*iqned and *hall be maintained with a

  • toraga oapacity limited to no more than 1170 fuel a**embli***

5.7 99MPQRIRT CX9LIC QB TRANSIENT LIMIT 5.7.1 Th* ccmponent* identified in Table 5.7-1 are d**iqned and *hall b*

maintained within th* cyclic or tran*i*nt limit* of Table s.1-1.

SALEM - tJHIT 2 5-5 Amendment No. 107

Retrieved from "https://kanterella.com/w/index.php?title=ML18100A935&oldid=1938919"