ML20136F862

Forwards Addl Info to Suppl Integrated Reactor Vessel Matl Surveillance Program Re Comparisons of Design & Operating Features of Four Reactors

ML20136F862
Person / Time
Site:	Nine Mile Point, Columbia, LaSalle, 05000000
Issue date:	11/18/1985
From:	Mangan C NIAGARA MOHAWK POWER CORP.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
(NMP2L-0536), (NMP2L-536), NUDOCS 8511220207
Download: ML20136F862 (20)

Text

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.N3 MINA NIAGARA InOHAWK POWER CORPORATION /300 ERIE BOULEVARD WEST, SYRACUSE, N.Y.13202/ TELEPHONE (315) 4741511 November 18, 1985 (NMP2L 0536)

Mr. H. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Denton:

?

Attached is additional information in response to a request by Mr. B. Elliott, of your staff. This material supplements the Integrated

' Reactor Vessel Material Surveillance Program which was' submitted to you in my letter dated September 30, 1985.

, _., provides a comparison between the pertinent characteristics of the surveillance specimen capsules materials for LaSalle 1 & 2 and Washington Public Power Supply System Nuclear Plant No. 2, and the limiting beltline plate and weld materials for Nine Mile Point Unit 2. provides additional information which compares the design and operating features of the four reactors. Attachment 2 shows that the plants are very similar.

Very truly yours, C. V. Man n Senior Vice President CVM/rla Attachments

.1061G xc: Project File (2)

R.A. Gramm, NRC Resident Inspector l

8511220207 851118

/

DR ADOCK 050 3

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The attached tables (A and B) are comparisons between the pertinent characteristics of the surveillance specimen basket materials for LaSalle 1 &

2 and Washington Public Power Supply System Nuclear Plant No. 2 (WNP-2) and the limiting beltline plate and weld materials for Nine Mile Point Unit 2.

The materials and vessel constructors utilized in the LaSalle 1 & 2 and WNP-2 vessels compare favorably with the materials and vessel constructor of the Nine Mile Point Unit 2 vessel.

l This provides additional justification for the use of LaSalle 1 & 2 and WNP-2 as comparison vessels to the Nine Mile Point Unit 2 vessel in the Integrated Reactor Vessel Material Surveillance Program.

i l

I Additional information to Item 2 of the September 30, 1985 letter, (C. V. Mangan (NMPC) to H. Denton (NRC))

Mr. B. Elliott (NRC) in a telepnone conversation on October 30, 1985, requested Niagara Mohawk to provide additional data that demonstrates that the design and operating features of the Integrated Surveillance Program reactors are similar.

As stated in the September 30, 1985 letter, LaSalle Units 1 & 2, Washington Public Power Supply System Nuclear Plant No. 2 and Nine Mile Point Unit 2 are General Electric Model BWR-5, 251 series vessels.

(251 represents the 251-inch vessel diameter.)

Attachment A is Table 1.3-1 through Table 1.3-7 of the Nine Mile Point Unit 2 Final Safety Analysis Report. These tables provide a comparison of design and operating conditions for the Integrated Surveillance Program reactors (excluding Zimmer).

Attachment B is a diagram of the typical BWR-5, 251 series vessel used by the subject plants.

As can be seen from the above data, the design and operating features of the' subject plants are sufficiently similar to permit an accurate comparison of the predicted amount of radiation damage as a function of total power output.

Additionally, as stated in item 6 of the September 30 letter, data sharing will include the cumulative power output as well as the analysis of the materials samples.

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. TABLE'A: PERTINENT CHARACTERISTICS OF THE SURVEILLANCE SPECIMEN CAPSULES HEAT NO.

VESSEL FOR BELTLINE TYPE WELD WIRE AND STEEL VESSEL PLATE SPECIMENS TYPE FLUX HEAT / LOT NO. OR WELD PLANT SUPPLIER CONSTRUCTOR IN BASKET 1 Cu %P (AND LOT N0.)

SPECIMENS IN BASKET 1 Cu 1P WELD PROCESS LaSalle 1 Lukens Combustion (cha rpy )****

.15*

.011 Type loo?

Type B-4 M00, IP3571/3958

.37*

Unknown Sutmerged Arc weld (SAW)

Steel Engineeering C6345-1 (Lot No. 3958)

(Weld Electrode) -

( tensil e )****

.1?*

.01 ?

Type 8018 Lot. ABEA

.04*

Unknown Shielded Metal Arc Weld C6318-1 LaSalle 2 Lukens Chicago Bridge C9481-1

.11 *

.008 Linde 174 INP94 (RACO) Neat / Lot No.

Steel

& Iron Nuclear (Lot No. 0342)

• • SP7397/0342

.03*

Unknown SAW

• • • 5P7397/0347

.03*

Unknown SAW WNP-2 Lukens Chicago Bridge B5301-1

.14

.01 7 Linde 174 Steel

& Iron Nuclear (Lot No.1714)

INP99 (RACO) Neat / Lot No.

.03

.011 SAW

• • 3P4066/1?l4

• • • 3P4966/1714

.03

.011 SAW Identified in LSCS FSAR as preliminary information Single Wire Process, Submerged Arc Weld Tanden Wire Process, Submerged Arc Weld The composition of this material is based on the Materials Certificate Report e

l b

TABLE f: PERTINENT CHARACTERISTICS OF THE LIMITING BELTLINE PLATE AND WELD MAT HEAT NO. FOR LIMITI E TYPE WELD WIRE (AND VESSEL NNP2 BELTLINE PLATE HEAT / LOT NO.) FOR THE STEEL VESSEL

( Also used in TYPE FLUX NW 2 VESSEL BELTLINE PLANT. SUPPLIER CONSTRUCTOR Surveillance Program 1 Cu 1P (AND LOT NO.)

LIMITIE WELD 1 Cu 1P WELD PROCESS C3187 2

.11

. 01 7 Linde 174 INIM (RACO) Heat / Lot No.

Suteerged Arc Weld (SAW)

IMP 2 Lukens Chicago Bridge i Steel

& Iron Nuclear

& C3s47-1

.11

.012 (Lot No. 0331) ' ( **5P6?148/0331 )

02

.013

(***5P67148/0331 )

01 4

.011 SAW

- CO Single Wire Process, Submerged Art Weld Tanden Wire Process, Submerged Arc Weld e

1 9

1 I

• [

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O SO SO Nine Mile Point Unit 2 FSAR TABLE 1.3-1 COMPARISON OF NUCLEAR STE15 SUPPLY SYSTEM DESIGN CHAR ACTERISTICS Nine Nile Point WPPSS Zinner La Salle

_Hait_2_

Hn11_2 En11_1 Halls _1 d IjiERNAL AND llIDPAULIC DESIGN (Section 4.4)

Bated power, NWt 3,323 3,323 2,436 3,293 l

Design power, NWt (ECCS design basis) 3,463 3,468 2,550 3,434 Steam flow rate, millions lb/hr 14.263 14.295 10.477 14.166 Core coolant flow rate, sillions lb/hr 108.5 108.5 78.5 106.5 Feedwater flow rate, millions 1b/hr 14.564 14.256 10.477 14.127 System pressure, nominal in steam done, psia 1,020 1,020 1,020 1,020 I

28 Average power density, kW/1 49.15 49.15 50.51 50.0 Miniana critical power flux ratio (MCPR) 1.24 1.24 1.24 1.28 Coolant enthalpy at core inlet, Btu /lb 527.5 527.6 527.4 527.1 Core max exit voids within assemblies 76.2 79 75 76 Core average exit quality, % steam 13.10 13.5 13.2 13.2 Feedwater temperature, OF 420 420 420 420 H2E19n E9E9E_Esatias_Iast9E Maximum relative assembly power 1.40 1.40 1.40 1.40 Arial peaking f actor 1.40 1.4 1.4 1.40 Egglear pggign_JEirst Corel See ( O.

e Po a

3:=

Amendmen t 21 1 of 4 September 1985

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-l Mine Nile Point Unit 2 FS&R TABLE 1.3-1 (Cont)

Nine.Eile Point WPPSS Zimmer La Salle

_Rait 2 Ha11_2 2111_1 Raits-1. 2 E91LREEHlXIE&LDHIEE (ssctions 4.2 and 7.6)

I" Inel assashlr sse (+>.

IssLassa l si sse (+>.

InsLEs11 sis l

sse ( + >.

InsLGhannsk l ai sms (+>.

E9ER_lEERahl1 sse (+>.

&Dozdment 21 2 of 4 September 1985 1

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Nine Mile Point Unit 2 FSAE TABLE 1.3-1 (Cont)

Nine Mile Point WPPSS Zimmer La Salle Unit ?_

Unit 2 Unit 1 Units 1,

2 Reactor control system Movable control rods; variable forced coolant flow Method of varying reactor power No. movable control rods 185 185 137 185 Type of control roddrives Bottom entry; locking piston Shape of movable control rods Cruciform Cruciform Cruciform Cruciform Pitch of movable control rods 12.0 12.0 12.0 12.0 Control material in movable rods B.C granules compacted in SS tubes Type of temporary reactivity Burnable poison; gadolinia-urania fuel rods control for initial core Inccre Neutron Instrumentation Local power range monitors (LPRM)

Total LFRM detectors 172 172 124 172 No. of incore LPPM penetrations 43 43 31 43 No. of IPRM detectors per penetration 4

4 4

4 Bange Approximately 1% power to 1255 power Average power range monitors (APBM)

No. detectors 6(43 6(a) 6(83 6(aa Approximately 15 power to 125% power Range Source range monitors (SRM)

No. detectors 4

4 4

4 Source to 0.001% power Range Intermediate range monitors (IRM)

No. detectors 8

8 8

8 No. flux-mapping neutron detectors 5

5

~'

0.001-10% power 0.001-10% power Range 0.001-10% power 0.001-10% power 4

5 j

No. and type of incore neutrcn scurces 7Sb-Be 7Sb-Be SSb-Be 7Sb-Be REACTOR VESSEL DESIGN (Section 5.3)

Material Low-alloy steel / Carton steel /

Low-alloy Carbon steel /

stainless clad stainless clad steel / stainless stainless clad Design pressure, psig 1,

m -

1,250 1,250 1,250 cesign terferature,

• E 575 575 575 575 Inside diameter, ft-in 20-11 20-11 18-2 20-11 Inside height, ft-in 72-5 72-11 69-10 72-11 3 of.4

EWMWWMEUm n

Nine Mile Point Unit 2 FSAR TABLE 1.3-1 (Cont)

Nine Mile Point NPPSS Zinner La Salle

_ Unit 2 Unit 2 Ug11_1 gnits 1, 2 sinimum base metal thickness (cylindrical 6.1875 6.75 5.375 6.75 section), in Miniaun cladding thicxness, in 1/8 1/8 1/8 1/8 EE AGI2.LC90 L &EI_EIGIECHLEIIO!_D E S I G N (Sections 5.1, 5.2, and 5.4)

No. recirculation loops 2

2 2

2 Design pressure Inlet leg, psig 1,250 1,250 1,250 1,250 outlet leg, psig 1,650(2) 1,650(2) 1,6 75( a) 1,650(2) 1,550(3) 1,550(3) 1,575(3) 1,550(3)

Design temperature, OF 575 575 575 575 Pipe diameter, in 24 24 20 24 Pipe material, AISI 316K 304/316 304/316 304/316 Recirculation pump flow rate, gpa 47,200 47,250 32,500 47,250 No. jet pumps in reactor 20 20 20 20 HAI!_JIE1H_LIHEE (Section 5.4)

No. steam lines 4

4 4

4 Design pressure, psig 1,250 1,250 1,250 1,250 Design teap, OF 575 575 575 575 l

Pipe diameter, in 26/28 26 24 26 Pipe material Carbon steel Carbon steel Carbon steel Carbon steel

( a 3 Channels of monitors from LPBM detectors (a) Pump and discharge piping to and including the discharge block valve.

(3) Discharge piping f rom discharge block valve to vessel.

(*) General Electric Licensing Beport. General Electric Standard Application

{ 28 for Beactor Fuel.

NEDE-24011-P-A (latest approved revision).

Amendmen t 21 4 of 4 September 1985

- 3).

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I Nine Mile Point Unit 2 FSAP TABLE 1.3-2 COMPARISON OF ENGINEERED SAFETY FEATURES DESIGN CHARACTERISTICS Nine Mile Point WPPSS Zimmer La Salle Unit 2 Unit 2 Unit 1 Units 1,

2 EMERGENCY CORE COOLING SYSTEMS (Systems sized on design power)

(section 6.3)

Low Pressure Core Spray System No. loops 1

1 1

1 Flow rate, gpm 6,350 4 128 psid 6,250 a 122 psid 4,625'8 119 psid 6,250 a 122 psid High Pressure Core Spray System No. loops 1

1 1

1 Flow rate, gpm 1,550 a 1,130 psid 1,650 a 1,110 psid 1,330 a 1,110 psid 1,650 a 1,110 psid 6,350 a 200 paid 6,250 a 200 psid 4,725 a 200 psid 6,250 a 200 psid Automatic Depressurization System No. systems 1

1 1

1 No. relief valves 7

7 6

7 Low Pressure coolant Inject ion (

• 1 No. LPCI systems 1

1 1

1 No. pumps 3

3 3

3 Flow rate, gpm/ pump 7,450 a 26 paid 7,450 a 20 psid 5,050 a 20 psid 7,067 a 20 psid AUXILIARY SYSTEMS Residual Heat Removal System (section 5. 4. 7)

No. Loops 2

2 2

3 No. Pumps 2

2 2

3 Flow rate, gpm/ pump (23 7,450 7,450 5,050 7,450 Duty, millions 41.6 41.6

30. 8 46.6 Btu /hr/ heat exchangercan No. heat exchangers 2

2 2

2 5,050 8,400 Primary containment cooling 7,450 7,450 node flow rate, gpm(

• 3 1 of 2

f-~

g 7

Nine Mile Point Unit 2 FSAR TABLE 1.3-2 (cont)

Nine Mile Point WPPSS Zimmer La Salle Unit 2 Unit 2 Unit 1 Unit 1,

2 Service Watcr System (Section 9.2.1)

Flow rate, gpm/RHR heat exchanger 7,400 7,400 5,000 7,400 No. pumps 6

4 4(*)

4 Reactor Core Isolation Cooling System (section 5.4.6)

Flow rate, gpm 600 8 1,173 psia 600 a 1,120 psid 400 3 1,120 psid 600 4 1,120 psia reactor pressure reactor pressure Fuel Pool cooling and Cleanup System (Section 9.1.3) capacity, millions Btu /hr 15.0 7.6 6.9 8.0 Standby Gas Treatment System (Section 9.3.5) charcoal bed design, Ib charcoal 2 independent 2 trains 2 trains, 2 independent trains, trains 2,000 lb/ train 3,700 lb/ train 1,360 lb/ train total 4,000 lb/ train 7,400 total Ib 2,720 lb total Design efficiencies, %

Elemental iodine 99.0 99.0 99.0 90.0 Crganic iodine 99.0 99.0 99.0 90.0 0.3u particles 99.97 99.97 99.0 99.97 System flow, cfm 3,500 scfm/ train 4,000 scfm/ train 2,300 scfm/ train 4,000 scfm/ train (8 3A mode of residual heat removal system.

(2 3 capacity during reactor flooding made with two or three pumps running.

(3 3 Heat exchanger duty at 20 hr following reactor shutdown.

(*3 Includes HPCS service water pumps.

2 of 2

^.

g.

Nine sile Point Unit 2 FSAR TABLE 1.3-3 COMP ARISON OF CONTAIN5ENT DESIGN CHAP ACTERISTICS Mine sile Point SPPSS Zinner La Salle ggit 2 gn11_2 gail_1 Units 1.

2 l

2i ErinaII_G9Ettinnant'83 (Section 3.8)

Type Over 5 under Over 6 under Over 6 under Over S under pressure pressure pressure pressure suppression suppression suppression suppression Mark II Hark II Mark II Mark II construction Reinforced Steel free-Concrete pre-Concrete concrete standing stressed steel post-tensio ned steel liner liner steel liner Dryvell Frustus of come, Frustum of cone, Frustus of cone, Frustus of cone, upper portion upper portion upper portion upper portion Pressure suppression Cylindrical Cylindrical Cylindrical Cylindrical chamber lower portion lower portion lower portion lower portion with elliptical bottos Pressure suppression chamber -

45 45 45 45 internal design pressure, psig pressure suppression chamber -

4.7 2

2 5

external design pressure, psig Dryvell - internal design 45 45 45 45 pressure, psig Dryvell - external design 4.7 2

2 5

pressure, psig Dryvell free volume, ft3 303,418 200,540(2) 180,000(33 221,518 as Pressure suppression chamber 192,028 144,184(*3 93,000 166,400 free volume (min), ft3 Pressure suppression pool 154,79acs) 112,197 102,120 109,096 vater volume, ft3 Amendment 21 1 of 3 September 1985

_7_-_.

.A N

Nine Nile Point Unit 2 FSAP TABLE 1.3-3 (Cont)

NNP WPPSS Zineer La Salle

_Init 2_

_ gait _2 Enit 1 Enits_1t_1 Submergence of vent pipe belos 9.5 min 11.67 min 10 12 otypression pool surface, ft 11.0 max 12.00 mar Design environmental temperature 340 340 340 14 0 c.f dryvell, *F Design environmental temperature 275 275 275 275 cf pressure suppression chamber, *F Dowacomer vent pipe 1.37(*)

1.9

2. 17

1. 9 pressure loss factor l"

Break area / total vent area 0.0108 0.0105 0.008 0.0105

)

Calculated marious pressure 39.7 35.7 40.4 34 citer blowdown to dryvell, psig calculated maximum pressure 34.0 28.0 35.6 28 in suppression chamber, psig calculated maximum initial 50 35 35 50 I

pressure suppression pool temperat ure rise, *F Leakage rate, % free voluee/ day 1.1 a 200*F 0.5 a 2000F 0.635

0. 5 et 45 psig and 340*F BitELSE.B9ildlBE_I!eS11ggs 3.8 t,_fz2L t

1 controlled Controlled Controlled Controlle5 Type

leakage, leakage,

leakage, leakage, elevated elevated elevat ed elevated

)

release ( 7 3 release release release

~

)

Construction l

Lower levels Reinforced Beinforced Peir: force 5 Rein forced concrete concrete concrete esacrete Upper levels Steel super-Steel super-Steel super-Steel super-structure and structure and structure and structure and siding siding siding siding Steel decking Steel decking Steel decking Steel deckf ag Baof 2 of 3 January 198%

Arendaent 17

3 u Nine Mile Point Unit 2 FSAB TABLE 1.3-3 (Cont).

Nine Mile Point WPPSS Zimmer La Salle Unit 2 Unit 2 Unit 1 Units 1, Internal design pressure, psig 0.25 0.25 0.25 0.25 Design inleakage rate, 100 100 100 100 5 free volume / day at 0.25 in Ha0

(

• 3Where applicable, containment parameters are based on design power.

(23 Maximum water in suppression pool.

( 3 3 Includes the vent volume.

(*3 Maximum value.

(SDAt high water level.

(63 Includes entrance and pipe friction.

(rafor accident conditions.

3 of 3

Nine Mile Point Unit 2 FSAR TABLE 1.3-4 COMPARISON OF ELECTRICAL POWER SYSTEM DESIGN CHARACTERISTICS Nine Mile Point WPPSS-Zimmer La Salle Unit 2 Unit 2 Unit 1 Units 1,_2 Cffsite Power System (Section 8.2) cutgoing lines (No.-rating) 1-345-kV 1-500-kV 3-345-kV 2-345-kV (per unit)

Incoming lines (No.- ra ting) 2-115-kV 1-230-kV 1-69-kV 2-345-kV 1-115-kV 1-345-kV (per unit)

Onsite ac Power System (Section 8.3.1)

Normal station service 1

2 1 (unit 1 per unit transformers auxiliary)

Reserve station service 3(33 2

2 1 (system aux) transformers Standby diesel generators 3t*8 3(23 3

3(33 4,160-V ESF buses 3(23 3(*3 3

3 ESF buses 3-600-V(23 3-480-Vtas 5-480-V 4-480-V de Power Supply (Section 8. 3. 2) 4-24-V Batteries (No.-vcits) 6-12 5-V( * >

5-125-v(*3 3-125-V 3-125-V 4124-v 1-250-v 1-250-V 1-250-v 2-24-V Buses (No.-volts) 6-125-V(*)

5-125-V(*)

3-125-V 3-125-V 2t24-V 1-250-V 1-250-V 1-250-V (33 Includes one auxiliary boiler transformer.

ca3 Includes an HPCS diesel generator.

(3 3Five total for 2 units. Cne serves either unit.

(*3HFCS battery and bus included.

1 of 1

i Nine Mile Point Unit 2 FSAR TABLE-1.3-5 COMPAR1 SON OF RADIOA;TIVE WASTE MANAGEMENT-DESIGN CHARACTERISilCS Mine Mile Point WPPSS Zimmer La Sa l le Unit 2 Unit 2 Unit 1 Units 1.2 Galeous Radwaile

( Sect ion I I. 3 )

Design basis, noble gases, 100,000 after 100,000 a f te r 100,000 after 100,000 after uci/sec 30 min decay 30 min decay 30 min decay 30 min decay Process treatment Recomb i ne r Low temperature Chilled Recombiner ambient charcoal cha rcoa l charcoal ambient charcoa l No. beds 8

8 5

8 20 Design condenser in-leakage, cra 30 30 12.5 21 Release point, height 430 (stack) 230 172 370 above ground, rt 181 (vent) liquid _Radwaste*

( Section 11.?)

lanatment nr:

Floor drains I or [,

I, D F. D returned F,

[ returned E, D returned l

returned to con-to condensate to condensate to condensate densa te storage, storage sto rage s to ra ge concentrates to radwaste solidification

[quipment drains I, D returned I, D returned F. D returned I, D returned to condensate to condensate to condensate to condensate storage storage storage sto rage Chemical waste E

F. D returned N, E, D returned E, D concen-E, D concentrates to condensate to condensate trates to solid to solid radwaste, storage, concen-sto ra ge ra dwa s te, dis-distillate recycled trates to radwaste tillate recycled solidification Amendment 20 1 of 2 July 1985 i

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Nine Mile Point Unit 2 FSAR TABLE 1.3-5 (cont)

Mine Mile Point WPPSS Zimmer La Salle Unit 2 Unit 2 Unit 1 Units 1.2 Lieuid Radwaitt (Section 11.2)_

Laundry weste -

F, Chemical addition R, d i scha rged R, d i scha rged F, E, sent to circulating water d i scha rge

• Laundry will be processed offsite at Nine Nile Point Unit 1.

KEY: D = Demine ra l i ze r E = Evaporator or concentrator F = Filter N = Neutralized

-R = Reverse osmosis

' 2 of 2

?

Nine Bile Point Unit 2 FSAR TABLE 1.3-6 CONPARISON OF POWER CONTE 9SION SYSTEN DESIGN CH ARACTERISTICS Eine Nile Point BPPSS Zinner*

La Salle

__Hn11_2_

voit 2 Ea11_1_

voits 1 2 De3 iga power, Nst 3,463 3,468 2,550 3,434 Design power, sue, gross 1,202 1,205 883 1,122 Ge3Grator speed, SPB 1,800 1,800 1,800 1,800 De: Iga steam flow, Ib/hr 14.3 x 106 75.0 x 106 11.0 x 10*

14.2 x 106

[ as I

Trrhine inlet pressure, psia 985 17 0 965 965 I Itime_1Janas_22mina (section 10.4.4)

Cepecity, percent of turbine 25 25 25 25 d sign steam flow Rain condessgg (Section 10.4.1)

Heat removal capacity, Btu /hr 7,830 x 106 7,702 x 106 7,053 x 10*

7,609 x 10*

EiEEEla1152_MR12E_SY412m (Section 10.4.5)

52. Pump s 6

8 3

3 Flce rate, gpa/ pump 105,000 82,000 150,000 210,000 E2astasale_RE4_Ettduater HIsists (Section 10.4.7)

Design flow rate, Ib/hr 14.917 x 106 14.260 x 106 10.971 x 106 14.127 x 106 No. condensate pu'aps 3 running 3 running 3

3 plus 1 spare No. condensate booster pumps 3 running 3 running 3

3 plus I spare Ms. feedwater pumps 2 running 2 running 2

3 1 standby Coedensate pump drive ac power ac power ac power ac power Cecdensate booster pump drive ac power ac power ac power ac power F?odwater pump drive ac power Turbine Turbine Turbine 2 Motor 1 eIedicates parameters at rated power.

Areadsent 21 1 of 1 September 1985

E i,

sline Mile Point Unit 2 FSAR TABLE 1.3 -

COMPARIS001 Of STRUCTURAL DESIGIO CHARACTERISTICS ~

Nine Mile Point WPPSS Zimmer La Salle Unit 2 Unit 2 Unit 1

-Units 1.2 Elevated Release Point (Section 11.3.3)

Type Stack, vent Vent Vent Vent Construction Stack - Reinforced -Steel Steel Steel concrete l-V.nt - st I Height (above g round ), ft 430 (stack) 200 172 370 187 (vent)

Egismic Desien (Section 3.7)

Ope ra t i ng ba s i s ea rthqua ke Horizontal, g 0.075 0.125 0.10 0.10 Vertical, g 0.075 0.07 0.07 Safe shutdown earth-quake Horizontal, g 0.15 0.250 0.20 0.20 Vertical, g 0.15 0.14 0.14 Wind Desian

( Sec t ion 3. 3 )

Maximum sustained, aph 90 100 90 90 Tornado Rotational, aph 290 300 300 300 Translational, sph 70 60 60 60 Total, aph 360 360 360 360 Amendment 4 1 of 1 September 1983

Attachment B

-~

(

TYPICAL BWR-5, 251 SERIES VESSEL REACTOR VESSEL HE AD TOP HEAD COOLING

}

SPRAY NOZ2LE

""*'L^i W Uh! N L

U STEAMDRYER ASSEMSLY-g SH U H DA GNMENT AND GUIDE BARS p

i STE AM Ol/TLET NOZZLE k

l kN p STEAM SEPARATOR AND w

,RO s,l STANOPIPE ASSEM0LY F EEDWATER INLET NOZZLE

," P,'

FEEDWATER SPARGER

.h TOP FUEL GUIDE SHROUD HEAD %

xg

' j CORE SPRAY -

SUPPLY HEADER l

,a5 p

l SHROUD HEA0 l

IL FUEL ASSEMSLY l

HOLD DOWN BOLTS Ihl

/

2 COf E SPRAY SPARGER FUEL SUPPORT PIECE I 'p, l ]

FLOW INLET INTO kh,!

8UND E 4

IN CORE FLUX

- ~

MONITOR ASSEMBLY G

I

)

gp b

CORE PLATE ASSEM8LY l

R EclRCULATING WATER l

INLET NOZZLE

,j VELOCITY LIMITER JET PUMP ASSEMBLY g

R ECIRCULATING WATER

'y OUTLET NOZZLE DIFFUSER ' ^

CONTROL ROD GUIDE TU8E N

ANO $HR

(

71 bl SUPPORT PLATE N

CONTROL ROD DRIVE HOUSING

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _