ML18096A067

Proposed Tech Specs to Support License Change Application 90-14 Re Fuel Assembly Enrichment Increase

ML18096A067
Person / Time
Site:	Salem
Issue date:	06/14/1991
From:	Public Service Enterprise Group
To:
Shared Package
ML18096A066	List: ML18096A065 ML18096A067
References
LCA-90-14, NUDOCS 9106210009
Download: ML18096A067 (7)

Text

ATTACHMENT 2 TECHNICAL SPECIFICATION PAGES WITH PEN AND INK CHANGES LICENSE CHANGE APPLICATION 90-14, NLR-N91087 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 5-4 5-5 5-5 5-4 5-5 5-5

!:IS IGN FEATURES DESIGN PRESSURE AND TEMPERATL'RE 5.2.2 The reactor containment building is designed and shall be maintained for a maximum internal pressure of 47 psig and an air temperature of 271°F.

5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 CONTROL ROD ASSEMBLIES 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 contain a nominal 142 inches of absorber material.

The nominal values of absorber material shall be 80 percent silver, 15 percent indium and 5 percent cadmium.

All control rods shall be clad with stainless steel tubing.

5.4 REACTOR COOLANT SYSTEM OCS IGN FEATURE AND TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be maintained:

SA LEM -

UN IT l 5-4 Amendment No. 80

DESIGN FEATURES

a.

In accordance with the code requirements specified in Section 4.l of the FSAR. with allowance for normal degradation pursuant to the applicable Surveillance Requirements, b*.

For. a pressure 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 12,811!.100 cubic feet at a nominal Tavg of 576.7°F.

s.*s MffiOROLOGICAL TOWER LOCATION

• 5.5.l The meteorological tower shall be located as shown on Fi gu re 5. 1-1.

5.6 FUEL STORAGE CRITICALITY spent fuel orage racks a ~ designed and maintained wit a nominal 21 nch center-to enter distance fuel assembli s and a nomi 1 10.5 inch c ter-to-center stance betwee spent fuel ssembl i es pl ed in the sto* ge racks to en re a k ff equ

• a 1 ent to~ 0.95 itn the stor ge pool fille with unborated ater. TRe k f of

< 0.95

• eludes a con rvative allo nee of 2.2%

~k for uncertai es.

DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 124'8".

CAPACITY designed and shall be maintained

,.,.,._,__,._,_,_-=-.~,_,_,._~~~...._J.-Jr-=_,__,,~~...!..l.1L--""".i.+-'LUL1oLLL~~_._,.el assemblies.

SALEM - UNIT 1 5-5 Amendment No

• 3 3, s s

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

a. A keff equivalent to less than or equal to 0.95 with the storage rack filled with unborated water. This valve of keff includes a conservative allowance of:

1.

2.2% delta k/k uncertainty for all standard and V5H fuel assemblies, and

2.

An additional 0.7% delta k/k uncertainty for standard and V5H fuel assemblies containing Integral Fuel Burnable Absorber (IFBA) pins.

b.

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

c.

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

d.

Standard or Vantage 5H fuel assemblies with maximum enrichment of 4.55 w/o U235 and a kinf less than or equal to 1.453 in the core geometry at 68°F with no soluble boron.

5.2.2 The reactor c o~ ta inm e i t b~ilc~n ; i s d es i g ~ ed and shall be ~ a ;n :~,~ ~~ '-r a m a xim~m int er r.al pressure of 47 ps ig ana an ai r ten?erature of 271°F.

5.3 REAC70R co~ ~

FUEL ASSE ~ 3 LI ES 5.3.l The reactor core shall contain 193 fuel assemblies with each fuel assembly normally containing 264 fuel ruds clad with Ziracloy-4 except t hat limited substitution of fuel rods by filler rods consisting of Zirac loy-4 er stainless steel or by vacanc ies may be mace if justified by a cycle spec i fic reload anal sis.

Each fuel rod shall hav~ a nominal active fuel len t h of 143. 7 inches.

he ini al co;e lea *ng shall have rnaximu:'il enrich

r. ':

perce

• U-235.

Reload fuel hall be simila in physical de gn to lea ng and all have a xi mum enrichme

• of 4,05 weigh percent CONT~O L ROD ASS EMS LIES.

5.3.2 The reactor core shall contain 53 full length and no part length contro l rod assemblies. The full length control rod assemblies shall conta i n a n c ~in a l 142 inches of absorber material.

The nominal values of absorber materi al shall be 80 percent silver, 15 percent indiun and 5 percent cadmium.

All cont,.c1

!" O~ s shall be clad with stainless steel tubing.

5.4 REACTOR COOLANT SYSTEM CES !GN FEATURE AND TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be ma i ntained:

VOLli."IE

a.

In accordance with the code requirement. specified in Section 4. 1 of the FSAR, with allowance for normal degradation pursuant to tne applicable Surveillance Requirements,

b.

For a pressure of 2485 psig, and

c. For a temperature of 650°F, except for the pressurizer which is 680°F.

5.4.2 The total water and steam volume of the reactor coolant syste~ i s 12,811.:, 100 cubic feet at a nominal Tavg of 581.0°F.

SA LEI~ -

UN IT 2 5-4 Amendment No. 54

DESIGN FEATURES 5.5 METEOROLOGICAL TOWER LOCATION 5.5. 1 The meteorological tower shall be located as shown on Figure 5. 1*1.

5.6 FUEL STORAGE CRITICALITY 5.6. 1 The new and spe fuel storage ra s are designed and sha

a.

A k uivalent to less an or equal to 0.95 w n flooded with unb!i ed water, which ludes a conservative lowance of 2.2%

del k/k for unce ties.

b.

A no*inal 21 inc center-to-center dista e for new fuel stor e racks and 10.i fnch enter-to-center distanc for* spent fuel star DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to

• prevent inadvertent draining of the pool below elevation 124'8".

. CAPACITY 5.6.3 TM fuel 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.7. 1 The cQ111Ponents fdentfffed fn Table 5.7-1 are designed and shall be maintained within the cyclic or transient lf*its of Table 5.7-1.

SALEM - UNIT 2 5-5 Amendment No. 22

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

a. A keff equivalent to less than or equal to 0.95 with the storage rack filled with unborated water. This valve of keff includes a conservative allowance of:

1.

2.2% delta k/k uncertainty for all standard and V5H fuel assemblies, and

2.

An additional 0.7% delta k/k uncertainty for standard and V5H fuel assemblies containing Integral Fuel Burnable Absorber. (IFBA) pins.

b. A nominal 10.5*fnch center-to-center dfstance between fuel assemblies placed in the spent fuel storage racks.

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

d. Standard or Vantage 5H fuel assemblies with maximum enrichment of 4.55 w/o U235 and a kinf less than or equal to 1.453 in the core geometry at 68°F with no soluble boron.