ML18102A199

Proposed Tech Specs,Adding Design Parameters for MSLB

ML18102A199
Person / Time
Site:	Salem
Issue date:	06/18/1996
From:	Public Service Enterprise Group
To:
Shared Package
ML18102A198	List: ML18102A197 ML18102A199
References
NUDOCS 9606250318
Download: ML18102A199 (3)

Text

Document Control Desk Attachment 2

• LR-N96126 LCR S96-06 SALEM GENERATING STATION UNIT NOS. 1 AND 2 FACILITY OPERATING LICENSES DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 CHANGE TO TECHNICAL SPECIFICATIONS CONTAINMENT DESIGN TEMPERATURE TECHNICAL SPECIFICATION PAGES WITH PROPOSED CHANGES The following Technical Specifications for Facility Operating License No. DPR-70 are affected by this change request:

Technical Specification 5.2.2 5-4 The following Technical Specifications for Facility Operating License No. DPR-75 are affected by this change request:

Technical Specification 5.2.2 5-4 Page 1 of 2

--~ --- 96062-so31 a96o6is-- ----

PDR ADOCK 05000272 P PDR

I I

DESIGN FEATURES PRESSURE A.NP TEMPERATURE S The reactor containment building is designed and shall be maintained for a maximum internal pressure of 47 psig and an air temperature of 27l"F.

5.3 R,EACTOR CORE FUEL ASSEMBLIES 5.3.l The reactor shall contain at least 193 fuel assemblies. Each assembly shall consist of a matrix of zircaloy or ZIRLO 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 NRC-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.

~Ot"J'ROL 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 I 4 RE.ACTOR COOtANI SYSTE."1:

DESIGN F'EATURE AND TEMPERAn.TRE 5.4.l The reactor coolant system is designed and shall be mainta*ined:

a. In accordance with the code requirement specified in Section ~.l of the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements, l b. For a pressure of 2485 psig, and I VOLUME

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 system is 12

• 811* +/- 100 cubic feet at a nominal Tavg of 581.0"F.

l The reactor containment is designed and shall be maintained for a maximum internal pressure of 47 psig. Containment air temperatures up to 351.3°F are acceptable providing the containment pressure is in accordance. with that described in the UFSAR.

SALE.'1 - UNIT 2 5-4 Amendment No .135

. DESIGN FEATURES PRESSURE AND TEMPERAT'JRE The reactor containment building is designed and shall be maintaine a maximum internal pressure of 47 psig and an air temperature of 27l"F.

5.3 REACTOR CORE F1JEL ASSEMBLIES 5.3.l The reactor shall contain at least 193 fuel assemblies. Eaci, assembl:;

shall consist of a matrix of zircaloy or ZIRLO clad fuel rods with an initia~

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 NRG-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 staf: approved codes and methods and shown by tests or analyses to comply with all fuel safety desi~n bases. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions.

C07'frROL ROD ASSL'1.BLIES 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 caC:::~*J.I::.

All control rods shall be clad with stainless steel tubing.

5,4 RL~CTOR COOLAJIT SYSTL~

DESIGN FEATURE AND TEMPERATURE 5.4.l The reactor coolant system is designed and shall be maintained:

The.reac~or containment is designed and shall be maintained for a maximum internal pressure of 47 psig. Containment air tempe~atures up to 351.3°F are acceptable providing the containment pressure is in accordance with that described i"n the UFSAR.

SALL'1. - UNIT 1 5 -4 Amendment ~o. 154