ML20072R956

Proposed Tech Specs,Rechanging Total RCS Water & Steam Vol to Reflect Inatallation of New SGs

ML20072R956
Person / Time
Site:	Millstone
Issue date:	09/01/1994
From:	NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20072R782	List: B14908, Application for Amend to License DPR-65,modifying Section 5.4.2 of TS by Changing Total RCS Water & Steam Volume to Reflect Installation of New SGs ML20072R956
References
NUDOCS 9409130368
Download: ML20072R956 (4)

Text

'

l l

4

, 1 i

Docket No. 50-336 B14908 ,

i 1

I l I

i I

Attachment 1 Millstone Unit No. 2 Proposed Revision to Technical Specifications Reactor Coolant System Volume Marked-Up Pages l

l l

September 1994 9409130368 940901 PDR ADOCK 05000336 P PDR,

,. N 3/01/90

. DESIGN FEATURES

(' -

Y.D.L21E S.4.2 The total water and steam volume of the reactor coolant system is y-10,000+700/0 c tic feet. .

t_ a. oce.ml 10,% G3 .

5.5 EMERGENCY CORE COOLING SYSTEMS 5.5.1 The emergency core cooling systems are designed and shall be maintained in accordance with the original design provisions contained in Section 6.3 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements.

5.6 FUEL STORAGE CRITICALITY 5.6.1 a) The new fuel (dry) storage racks are designed and shall be maintained with sufficient center to center distance between assemblies to ensure a k The maximum nominal fuel enrichment to be stored in these racks *4.50 N sweight

.95. percent of U-235.

b) Region A of the spent fuel storage pool is designed and shall be maintained with a nominal 9.8 inch center to center distance between storage locations to ensure a K s .95 with the storage pool filled with unborated water. Fuel assemblies Yored in this region must comply with figure 3.9-4 to ensure that the design burnup has been sustained.

c) Region B of the spent fuel storage pool is designed and shall be maintained with a nominal 9.8 inch center-to-center distance between storage locations to ensure K ff s .95 with a storage pool filled with unborated water. Fuel assemblid stored in this region may have a maximum nominal enrichment of 4.5 weight percent U-235. Fue' assemblies stored in this region are placed in a 3 out of 4 STORAGE PATTERN for reactivity control.

d) Region C of the spent fuel storage pool is designed and shall be maintained with a 9.0 inch center to center distance between storage locations to ensure a K f 5 95 with the storage pool filled with unborated water.

Fuel assemblie$ fstored in this region must comply with Figures 3.9-la or 3.9-lb to ensure that the design burn-up has been sustained. Additionally, fuel assemblies utilizing Figure 3.9-lb require that borated stainless steel poison pins are installed in the fuel assembly's center guide tube and in two diagonally opposite guide tubes. The poison pins are solid 0.87 inch 0.D.

borated stainless steel, with a boron content of 2 weight percent boron.

e) Region C of the spent fuel storage pool is designed to permit stora e of consolidated fuel and ensure a K f 5 0.95. The contents of conso idated fuel storage boxes to be stored ih khis region must comply with '

Figure 3.9-3.

MILLSTONE - UNIT 2 5-5 Amendment No. J#, SJ, J##,

"" ,195, J10.

( _ --

Docket No. 50-336 B1490Q Attachment 2 Millstone Unit No. 2 Proposed Revision to Technical Specifications Reactor Coolant System Volume Retyped Pages September 1994

i l l

l DESIGN FEATURES l

VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is a l nominal 10,981 ft*.

I

\

5.5 EMERGENCY CORE COOLING SYSTEMS l 5.5.1 The emergency core cooling systems are designed and shall be maintained l in accordance with the original design provisions contained in Section 6.3 of i l the FSAR with allowance for normal degradation pursuant to the applicable l l

Surveillance Requirements. l l

l 5.6 FUEL STORAGE CRITICALITY i

5.6.1 a) The new fuel (dry) storage racks are designed and shall be

maintained with sufficient center to center distance between assemblies to l ensure a k,,, s .95. The maximum nominal fuel enrichment to be stored in l these racks is 4.50 weight percent of U-235.

l l

b) Region A of the spent fuel storage pool is designed and shall be maintained with a nominal 9.8 inch center to center distance between storage locations to ensure a K.,, s .95 with the storage pool filled with unborated water. Fuel assemblies stored in this region must comply with Figure 3.9-4 to ensure that the design burnup has been sustained, c) Region B of the spent fuel storage pool is designed and shall be maintained with a nominal 9.8 inch center-to-center distance between storage locations to ensure K.,, s .95 with a storage pool filled with unborated water. Fuel assemblies stored in this region may have a maximum nominal enrichment of 4.5 weight percent U-235. Fuel assemblies stored in this region are placed in a 3 out of 4 STORAGE PATTERN for reactivity control.

d) Region C of the spent fuel storage pool is designed and shall be maintained with a 9.0 inch center to center distance between storage locations to ensure a K,,, s .95 with the storage pool filled with unborated water.

Fuel assemblies stored in this region must comply with Figures 3.9-la or 3.9-lb to ensure that the design burn-up has been sustained. Additionally, fuel assemblies utilizing Figure 3.9-lb require that borated stainless steel poison pins are installed in the fuel assembly's center guide tube and in two diagonally opposite guide tubes. The poison pins are solid 0.87 inch 0.D.

borated stainless steel, with a boron content of 2 weight percent boron, e) Region C of the spent fuel storage pool is designed to permit storage of consolidated fuel and ensure a K ,,1 0.95. The contents of consolidated fuel storage boxes to be stored in this region must comply with Figure 3.9-3.

MILLSTONE - UNIT 2 5-5 Amendment No. 79, 57, 197, otss lil, iff IF9, 177,