ML20004B040

Forwards Table of Structures,Sys & Components for Which Classification Re Quality Group & Const Code Stds Is Required.Table Should Be Completed & Encl Data Verified. Response Due in 30 Days

ML20004B040
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	05/19/1981
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:	Hoffman D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
References
TASK-03-01, TASK-3-1, TASK-RR LSO5-81-05-032, LSO5-81-5-32, NUDOCS 8105270145
Download: ML20004B040 (17)

Text

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h' May 19, 1981 Docket No. 50-155 ce L505-81-05-032 e

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Mr. David P. Hoffman Nuclear Licensing Administrator

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Consumers Power Company 2

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1945 W ParnallfRoad 1

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Jackson, Michigan 49201 ve

SUBJECT:

CLASSIFICATION OF STRUCTURES, SYSTEMS AND COMPONENTS SEP TOPIC III-l (BIG ROCK POINT)

Enclosed is a table of structures, systems and components for which classifica-tion with respect to quality group and construction code standards is required.

Seismic classification is being addressed as part of the overall seismic aesign reevaluation. Electrical power distribt. tion systems and instrunentation such as sensors and actuation devices are not addressed here for quality group, but will be considered for seismic adequacy.

You are requested to complete the following table and verify whether the data already entered is correct. Furthennore, we request the following infonnation:

1) For all systems and components supply the classification being used for Section XI testing.

2) Provide any supplemental quality assurance which was perfonned during con-struction such as testing, non-destructive examination, material trace-ability, etc. which would assist us in our review.

Your response is requested in 30 days.

Sincerely, Dennis M. Crutchfield, Chief Operating Reactors Branch No. 5 Division of Licensing

Enclosure:

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As stated AD

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Docket No. 50-155 Mr. David P. Hoffman Nuclear Licensing Administrator Consumers Power Company 1945 W Parnall Road Jackson, Michigan 49201

SUBJECT:

CLASSIFICATION OF STRUCTURES, SYSTEMS AND COMPONENTS SEP TOPIC III-l (BIG ROCK POINT)

Enclosed is a table of structures, systems and components for which classifica-tion with respect to quality group and construction code standards is required.

Seismic classification is being addressed as part of the overall seismic design reevaluation. Electrical power distribution systems and instrumentation such as sensors and actuation devices are not addressed here for quality group, but will be considered for seismic adequacy.

The plant seismic design was report d to e a seismic loading of 0.05g for the reactor enclosure and equip:nent he in while a loading of 0.025g was applied to the remainder of the plant he Reactor Depressurization System, RDS, was designed to more recent crit ia, as noted). The licensee will have to specify how interfaces were t ted in the application of seismic loadings of 0.025 and 0.05g if such iff ences are found to be important.

You are requested to complete the following table and verify whether the data already entered is correct. Furthemore, we request tha following information:

l l

1) For all systems and components supply the classification being used for l

Section XI testing.

2) Provide any supplemental quality assurance which was performed during con-struction such as testing, non-destructive examination, materialhrace-ebilicy, etc. whic5 would assist us in our review.

d*[

l Your response is requested in 30 days.

/

h Sincerely,

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Dennis M. Crutchfield., Chief Glainas Operating Reactors Branch No. 5 Division of Licensing /

5/ /81 cc: See. next. pige... SEPB : DL SEPB:D[N/). S-,-

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UNITED STATES e

't NUCLEAR REGULATORY COMMISSION E

O WASHINGTON. D. C. 20555 5-I May 19, 1981

.,,,n Cocket No. 50-iS5 LS05-81-05-032 Mr. David P. Hoffman Nuclear Licensing Administrator Consumers Power Company 1945 W Parnall Road-Jackson, Michigan 49201

SUBJECT:

CLASSIFICATION OF STRUCTURES, SYSTEMS AND COMPONENTS SEP TOPIC III-l (BIG ROCK POINT)

Enclosed is a table of structurer., systems and components for which classifica-tion with respect to quality group and construction code standardi is required.

Seismic classification is being addressed as part of the overall seismic design reevaluation.

Electrical power distribution systems and instrumentatica such as sensors and actuation devices are not addressed here for quality group, but will be can'sidered for seismic adequacy.

You are requested to complete the following table and verify whether the data already entered is correct. Furthermore, we request the following information:

1) For all systems and components supply the classification being used for Section XI testing.

2) Provide any supplemental quality assurance which was performed during can-struction such as testing, non-destructive examination, material trace-ability, etc. which would assist us in our review.

Your rescense is requested in 30 days.

Sincerely, j'

c Dennis M. Crutchfleld, C f

Operating Reactors Branc No. 5 Division of Licensing

Enclosure:

As stated cc w/ enclosure:

See next page i

o Mr. David P. Hof fman cc Mr. Paul A. Perry, Secretary U. S. Environmental Protection Consumers Power Co pany Agency 212 West Michigan Avenue Federal Activities dranch Jackson, Michigan 49201 Region V Office ATTN: EIS COORDINATOR Judd L. Bacon, Esquire 230 South Dearborn Street Consumers Power Conpany Chicago, Illinois 60604 212 West Michigan Avenue Jack son, Michigan 49201 Herbert Grossman, Esq., Chairman Atomic Safety and Licensing Board Joseph Gallo, Esquire U. S. Nuclear Regulatory Comission Isham, Lincoln & Beale Washington, D. C.

20555 1120 Connecticut Avenue Room 325 Dr. Oscar H. Paris Washington, D. C.

20036 Atomic Safety and Licensing Board U. S. Nuclear Regulatory Comission Peter W. Stekr. tee, Esquire Washington, D. C.

20555 505 Peoples Bui: ding Grand Rapids, Michigan 49503 Mr. Frederick J. Shon Atomic Safety and Licensing Board Alan S. Rosenthal Esc., Chairman U. S. Nuclear Regulatory Comission Atomic Safety & Licensing Appeal Board Washington, D. C.

20555 U. S. Nuclear Regulatory Comission Washington, D. C.

20555 Big Rock Point Nuclear Power Plant ATTN: Mr. C. J. Hartman Mr. John O'Neill, II Plant Superintendent Route 2, Box 44 Charlevoix, Michigan 49720 Maple City, M enigan 49C34 Christa-Maria Charlevoix Public Library Route 2, Box 108C 107 Clinton Street Charlevoix, Michigan 49720 Charlevoix, Michigan William J. Scanlon, Esquire Chairman 2034 Pauline Boulevard County Board of Su;ervisors Ann Arbor, Michigan 4B103 Charlevoix County Charlevoix, Michigan 49720 Resident Inspector Big Rock Point Plant Office of the Governor (2) c/o U.S. NRC Room 1 - Capitol Suilding RR #3, Box 600 Lansing, Michigan 48913 Charlevoix, Michigan 49720 Director, Criteria and Standards Mr. Jim E. Mills Division Route 2, Box 108C Office of Radiation Programs Charlevoix, Michigan 49720 (ANR-460)

U. S. Environmental Protection Thomas S. Moore i

Agency Atomic Safety & Licensing Appeal Boad Washington, D. C.

20460 U. S. Nuclear Regulatory Coccission Washington, D. C.

20555 I

i

e O

BIG ROCK POINT TABLE OF CONTENTS TITLE PAGE 1.

Structures..........................

I 2.

Reactor Coolant System....................

2 3.

Recirculation System.....................

2 4.

Emergency Systems 3

Liquid Poison System..................

3 Core Spray System 4

Backup Core Spray System................

5 Enclosure Spray and Backup System............

5 Emergency Cooling System................

Reactor Depressurization System.............

6 6

Fire Protection System.................

7 5.

Sa fe ty Re l i e f Va l ves.....................

7 6.

Reactor Coolant Pressure Boundary..............

7 7.

Isolation Valves.......................

7 8.

Containment Penetrations...................

7 9.

Control Rods.........................

7 10.

Control Rod Drive Housing..................

7 11.

Control Rod Drive Housing Supports............

7 12.

Control Rod Drive System...................

8 13.

Spent Fuel Pit Cooling System................

8 14.

Turbine Stop Valve Housing..................

8 15.

Condensate /Feedwater System.............. '...

8 16.

Main Steam System......................

9 17.

Reactor Water Cleanup System.................

9 18.

Reactor Shutdown Coolina System...............

10 19.

Reactor Cooling Water System.................

10 20.

Makeup and Condensate Demineralizer System..........

11 21.

Service and Instrument Air System..............

II i

22.

Standby Diesel Generator System...............

II l

23.

Service Water System.....................

Il

(

24.

Ventilation System.......................

II 25.

Reactor Recirculation Pump Seal System............

12

(

26.

Standby Electric Power Systems................

12 l

27.

Instrumentation and Controls.................

t i

t l

i m...

l Quality Group Seismic Classification II Plant (*I III Plant (2)

Section XI R.G. 1.29 Components / Subsystems R.G. 1.26 SRP 3.2.2 Design Classification SAP 3.2.1 Design Notes J

I.

Structures Splierical contatsunient A58tf 111 A5ML Sec. II Vill 7

Selsmic Category I

.059 (5) itC

& IX as modified I,y applicable Code cases Sup,> ort for Reactor Enclosure Plenum Seismic Catep ry I

.059 (5)

Stack II U8C Zone 1 1958 l

I Supports for Exhaust Stack 11 USC Zone 1 Plenum 1958 i

Water intake Structure Seismic Category i USC Zone 1 l

IM i

i II USC Zone 1 Turbine Building 1958 1

Control Room Seismic Category I USC Zone 1 1958 4

Waste 5toratje Vaults Seismic Category i USC Zone 1 1958 4

4 i

I

4 4

3

()uality Group Seismic Classification I3I Plant *}

I III Plant (2)

Section XI R.G. l.29 Components / Subsystems R.G. l.26 SRP 3.2.2 Design Classification SRP 3.2.1 Design Notes I

Spert fuel Storage Racks Seismic Category I

.059 (5) fuel Pit A$tE Sec. III 7

7 Seismic Category I

.05s.

(5)

Class 3 Structures Housing i

Liquid Radwaste Seismic Category i IABC Zone I i

1958 2.

Reactor Mlant System Reactor Vessel ASML Sec. til ASME Sec. I, Vllt

?

Seismic Category 1

.059 (5),(6)

Class 1

& Code Cases 1270N, j

1271N, 1273N 2

Reactor Vessel Supports Seismic Category I

.05g (5) e Reactor Vessel Internals ASHE Sec. til ASE Sec. VIII &

7 Seismic Category 1

.05g (5),(7)

Class 1 Applicable Code Cases 1

3.

Recirculation System Steam Drum A$ME Sec. Ill ASME Sec. Vill &

Seismic Category I

.059 (5)

Class 1 Applicable Code Cases Pumps ASME Sec. 111 A$tE Sec. VIII &

Seismic Category I

.05g (5), (7)

Class 1 Applicable Code Cases Valves (24", 20", 5" ASFE Sec. Ill ASA B.31.1 Selsnic Category I

.05g (5),(B)

Gates, 20* Butterfly on Class 1 1955 Each Recirc. Line)

I 4

t 4

'O 6

i Quality Group Seismic Classification I3I I4I III Plant (2)

Section XI R.G. 1.29 Plant Components / Subsystems R.G. 1.26 SRP 3.2.2 Design Classificatinn SAP 3.2.1 Design Notes Primary Piping (Up A5ME Sec. III ASA B.31.1 1955 &

Seismic Category I

.059 (5) to Drum)

Class 1 Code Cases N1, NT, N9 and N10 4.

Energencyjsteins i

Ligald.I'oison Sntg!

Piping and Valves Beyond AM4C Sec. III

?

?

Seismic Category I

.05g (5)

Isolation Valves Class 2 3,

Poison Tank ASME Sec til

?

i Seismic Category I

.05g (5)

Class 2 Nitrogen Bottles ASME Sec. III

?

?

Seismic Category I

.059 (5) 4 Class 2 N

Lore Spray A g em Pumpi ASME Sec. 111

?

?

Seismic Category I Ubc Zone 1 Class 2 1955 Piping, fittings, and A5ftE Sec. til

?

?

Seismic Category i

.059 (5)

Valves inside Contain-Class 2 sent J

e t

i t

I I

Quality Group Seismic Classification I4I III Plant (2)

Section XI R.G.1.29(

Plant Components /Subsysteac R.G. 1.26 i

SRP 3.2.2 Design Classi fica tion SRP 3.2.1 Design Notes l

Qerge_ncy Systems Cont.

Piping, fittings and Valves ASME Sec. 111 7

7 Seismic Category I UBC Zone 1 Outside Contairment Class 2 1955 Core Spray Nozzle ASME Sec. III USAS B.31.1, USAS

?

Seismic Category I

.05g (5)

B.31.7. Draft ASME

='

Code for Pumps &

Valves for Nuclear Service Suction Strainers Seismic Category I

.059 (5) i licat Exchanger Primary ASHI Sec. 111 7

7 Seismic Category i UBC Zone I Side Class 2 1955 l

Secondary Side ASME Sec. III 7

7 Seismic Category I UBC Zone 1 Class 3 1955 l

Dackup Core, Spray h ste:m 1

Piping. Fittings and Valves ASME Sec. 111 USAS B.31.1, USA?.

7 Seismic Category I

.05g (5) inside Contairment B.31.8 ASME Draft d

Code Piping. Fittings and Valves ASME Sec. Ill USAS B.31.1, USAS

?

Seismic Category I UBC Zone 1 Outside Contairment B.31.7 ASME Draft 1955

~

Code i

11uality Grous Seismic Classification III Plant (2)

Section XI R.G. 1.29( I Plant (4)

Components / Subsystems R.G. 1.26 SRP 3.2.2 Design Classification SRP 3.2.1 Design' flotes Eargency Systons Cont.

Core Spray Nozzle ASME Sec til USAS 8.31.1, USAS T

Seismic Category I

.05g (5)

Class 2 B.31.7 ASME Draft Code inclosure Spray and bc Wp'5yd em tiping. Fittings and ASME Sec. III 7

7 Seismic Category I

.05g (5)

Valves Class 2 Spray Rings ASML Sec. III 7

7 Seismic Category I

.05g (5)

Class 2 i

Leggency Coolinghmn En= rgency Condenser Shel) Side ASME Sec. III ASML with Code 7

Seismic Category I'

.05g (5)

Class 3 Cases 1270N.

1272N Tube Side ASML Sec. Ill 7

7 Seismic Category I

.05g (5)

Class 2 Piping. Fittings and ASME Sec. III 7

7 Selsmic Category I

.05g (5)

Valves (Tube Side)

Class 2

3 I

t Quality Group Seismic Classification II I4I III Plant (2)

Section XI R.G. 1.29 Plant Components /Sut>sys tems R.G. 1.26 SRP 3.2.2 Design Classification SRP 3.2.1 Design Motes Eme_rgency j stems Cont.

Pipings Fittings and ASME Sec. III 7

7 Seismic Category I

.05g (5)

Valves (Shel) Side)

Class 3 I

l i

e Reactor Depressurization hs t,,em 4

t Relief Valves ASME Sec. III 7

7, Seismic Category I Seismic Category l

Class I I

e I

Pipings Fittings and ASME Sec. 111 7

7 Seismic Category I Seismic Category Valves to Relief Valves Class I Discharge Lines to ASME Sec. III 7

7 Seismic Category I Seismic Category i

Steam Drum Enclosure Class !!

I j

fire Protection System v

y Pumpi (Diesel. Electric A*E Sec. Il s 7

7 Seismic Category I UBC Zone I l

and Jockey)

Class 2 1955 Pipings, Fittings and N ME Sec. Ill 7

7 Seismic Category I UbC Zone i 4

Valve %

Class 2 1955 a

l'

I Quality Gr gou Seismic Classification I3I I4I III Plant (2)

Section XI R.G. 1.29 Plant Components / Subsystems R.G. 1.26 SRP 3.2.2 Design Classification SRP 3.2.1 Design Notes 5.

Safety Relief Valves ASMC Sec. Ill 7

7 Seismic Category I

.059 (5)

Class 1 6.

Reactor Coolant Pressure ~

Boundary Piping from Reactor Vessel A$ME Sec til ASA B.31.1 - 1955

?

Seismic Category I

.05g (5) i Up to and including first Code Cases N-1. N-7, Isolation Valve Caternal N-9 M-10 i

to Contairment 1.

Isolation Valves A5t1E Sec. Ill ASA B.31.1 - 1955

?

Seismic Category I

.059 (5)

(Others than valves Class I Code Cases N-1. H-7, identified under item 8)

N-9, N-10 8.

Contalemeent Penetrations ASMi Sec. III

?

Seismic Category I

.05g (5) italves and Plping Class 2 9.

Control Rods Seismic Category i

?

10. Control Rod Drive Housing ASMC Sec. III

?

7 Seismic Category I

.059 (5)

Class 1 II. Control Rod Drive Seismic Category I

.05g (5)

~flousing Supporh

12. Control Rod Drive A5MC Sec. III 7

7 Seismic Category I

.05g (5)

System Class 2

a i

l Quality Croup Seismic Classification I3I I4I III I2I Plant Plant Sectior. XI R.G. l.29 Components / Subsystems R.G. l.26 SRP 3.2.2 Design Classification SRP 3.2.1 Design Notes

13. Spent Fuel Pit A5ME Sec. Ill 7

7 Seismic Category I

.059 (5)

CooTEghstem Class 3 4

14. Turbine Stop Valve Seismic Category I USC Zone I j

!!9us {pl.

1955 t

15. Condensate /Feedwater l

i I

S 51e*

J I.

i Piping from Outennost A$ML Sec. Ill ASA 8.31.1 1

Seismic Category I USC Zone I

+

Cont'ainment isolation Valve Class 2 1955 l

up to and including the Shut-J off Valve and Connected 1

i Pl;ing up to and includjpg) the First Shutoff Valvet.u Balance of feedwater Quality Group D hon-Seismic UBC Zone t System from Shutoff 1955

,e Valve to the Condenser t

16. !Qin Steam System Steam Line, Drum to it)V A5ME Sec. til ASA B.31.1

?

Seismic Category I

.05g (5) 7050 Class I Drain Line, from Steam-A5ML Sec. III ASA B.31.1

?

Seismic Category I

.059 (5)

Line to MOV 7065 Class 1 Steam Line, MOV 7050 to A5ML Sec. III ASA B.31.1

?

Seismic Category I

.025/.05g (11)

Stop Valve and Connected 3

Piping to First Shotof f Valve

--....e.

s 1

1 4

f)uality Grou2 Se:smic Classification l

I3I Plant (*I III Plant (2)

Section XI R.G. 1.29 Components / Subsystems R.G. 1.26 SRP 3.2.2 Mg Classification SRP 3.2.1 Design flotes Drain Line from Valve A5ME Sec. til ASA B.31.1

?

Seismic Category 1

.025/.05g (11)

MuV 7065 to CV 4101 Class 1

11. Heactor Wter Cleanup ASME Sec. III

1. 5A B.31.1 7

Selsmic Category I

.059 (5)

]

@ tem Class 1 Non. Regenerative Heat Exchanger

' Tube Side ASME 5ec. III 7

7 Selsmic Category I

.059 (5)

Class 1 j.

t Shell Side ASME Sec. III

?

?

Seismic Category I

.05g (5)

Class 3 I

13. Reactor Shutdown

~E ling system C

Pumps ASME Sec. III 7

7 Seismic Category 1

.059 (5)

Class 2 Heat Exchangers Tube Side AMel Sec. 111

?

?

Seismic Category I

.059 (5)

Class 2 Shell Side ASME Sec. III 7

7 Seismic Category I

.059 (5)

Class 3 i

4

}

4 Quality Group Seismic Classification II III 0I 2)

Plant Plant Section XI R.G. 1.29 Components / Subsystems R.G. l.26 SRP 3.2.2 Design Classi fica tion Siv 3.2.1 Design Notes Gland Cooiers i

Tube side ASME Sec. Ill 7

7 Seismic Category I

.059 (5)

Class 2 i

I l

Shell Side A5ML Sec. Ill 7

7 Seismic Category I

.059 (5)

Pipings. Fittings ALML Sec. til 7

7 Seismic Category I

.059 (5)

I and Valves Class 2

{

19. Reactor Cooling

~

l E ter Syst e Pusups ASHL Sec. Ill 7

7 Mon-Seismic USC Zone I Class 3 Category I 1955 Reactor Cooling ASHL 5et Ill

?

7 Mon-$eismic

.059 (5)

}

h ter Tank Class 3 Category I g

4 i

Pipings. Fittings ASMC Sec. Ill

?

7 Mon-Seismic

.05g (5) and Valves Class 3 Category 1

20. Makeugand Condensate ljemTeri1Trer System Condensate Storage Quality Group D Non-Seismic UBC Zone 1 i

Tank Category 1955 Piping and Valves From ASME Sec. til

?

7 Non-Seismit UBC lone i Hotwell to Condensate Clas 3 Category 1955 Storage Tank s

i

I i

Quality Group

' Seismic Classification I3I I4I III Plant (2)

Section XI R.G. 1.29 Plant Components / Subsystems R.G. 1.26 SRP 3.2.2 Design Classification SRP 3.2.1 Design Notes l

21. Service and Instrument Sce Note 12

?

?

See Note 12 USC Zone 1

(

ATiF tystem less,,

22. Standby Diesel Generator ASME Sec. Ill

?

7 Seismic Category i USC Zone 1 l

System Class 3 1955 l'

23. Service Idater System A$ tit Sec. Ill

?

?

Seismic t.ategory i USC Zone 1 l

Class 3 1955 g

l t

'24. Ventilation System l

l Control thxun Air Condition-Seismic Category i USC Zone 1 I

l ing Lines 1955 Instrument Room Ventila-Seismic Category I

.059 (5) tion

25. Reactor Necirculatluri Pump SE3T WieT Syilem-Piping and Valves ASME 5ec. III 7

?

Seismic Category I

.05g (5) l Class 1 Pump ASME Sec. III 7

7 Seismic Category I

.059 (5) lleat Exchanger Tube Side ASHE Sec. Ill 7

?

Seismic Category I

.059 (5) l Class I i

j Shell Side ASME 5ec. 111 7

?

Seismic Category I

.059 (5)

Class 3 I

i

ig e

6 i

4 Quality Group Seismic Classification I3I I4I III Plant Plant Section XI R.G. l.29 Components / Subsystems R.G. 1.26 SRP 3.2.2 Design Classification SRP 3.2.1 Design Notes

26. Standby Electric g

Power Systems Station Batteries Seismic Category I USC Zone 1 1955 Emergency Buses and Seismic Category I USC Zone i j

Other Electrical Gear 1955 g

and Power to Critical g

Equjpment

27. Instrumentation and foWrlo s Heactor Safety System Seismic Category I USC Zone 1 l

1955 Neutron Monitor System Control Rod Instrumentation Liquid Poison System Control l

Reactor Level Instrumentation Steam Supply System Instrumentation Process Radiation Munitoring Area & Personnel ibnitoring d

i

NOTES, SPECIFIC (1) Quality Standards are specified as Class 1, 2, 3 and quality group.

Those for the Reactor Coolant Pressure Boundary fall into Class 1 ard are defined in 10 CFR 50.55a. All others are defined in Regulatory Guide 1.26 and Section 3.2.2 of the Standard Review Plan.

(2) ASME - Indicates that ASME Boiler and Pressure Vessel Code was employed in design. Code sections, code cases and dates are identi-fied when references so indicate; omitted when absent from references.

For systems other than the following, information regarding applica-tion of ASME code criteria to design obtained from drawings:

a.

Primary (Recirculation System) b.

Backup Core Spray System c.

Core spray system (only the piping and valves added at the time of Backup Core Spray System installation).

d.

Reactor Depressurization System ASA - Indicates that ASA Power Piping Code B.31.1 was employed in design Code sections, cases and dates are identified when references so indicate; omitted when absent from references.

All other coce criteria are identified within the table.

Question marks appearing in the table indicate plant design information has not been obtained for these particular areas. The licensee will have to provide information necessary to complete the table.

l Completion will also require information regarding the extent of the application of the ASME and ASA cases to valves in systems not mentioned in this note but which coverage is noted in Table I (and in Bechtel Specification 3159 M-ll3).

(3) Seismic requirements fall into two categories, I and II.

I means that the com;,onent is required to comply with the requirements of Regulatory Guide 1.29 and Section 3.2.1 of the Standard Review Plan; II means that seismic requirements do not apply.

I(0BE) means that seismic requirements apply but that the seismic acceler-ation of the Operating Basis Earthquake, rather than that of the greater i

l Safe Shutdown Earthquake, applies.

l

(4) The Final Hazards Summary Report (Ref. 1) for the Big Rock Point Nuclear Power Plant reports that the reactor enclosure and equipment within is designed to withstand ground acceleration equivalent to 0.059; equipment and structures outside are designed withstand a ground acceleration of 0.025g.

The licensee will have to supply information regarding the interface, i.e., where the system is designed for 0.05 or 0.0259, when the system penetrates cor+ainment but only if such differences are deemed critical to the evaluation.

(5) Since the Uniform Building Code (UBC) does not clearly cover the reactor containment or concrete structures and equipment within, a seismic factor equal to the maximum expected ground acceleration at the site was used. The ground acceleration facto" used was 0.05 gravity. This is twice the factor required by UBC Zone 1 forces used at the plant for all other structures.

(6) Used Department of Commerce PB-151987 February,1959 for areas not defined in ASME Code.

(7) Codes used for pump casing design.

(8) Wall thickness of valves exceeds code requirements.

(9) Core spray system has no containment isolation valves.

(10) Shutoff valve is the first valve that is either normally closed or capable of automatic closure during all modes of normal reactor operation.

(11) Class break occurs at first valve of main steam line since there is only one main steam isolation valve.

(12) Portions of air systems required to perform safety function (i.e.,

gas or air supply to ADS and MSI valves) should be Seismic Category I and Class 3.

i l

i l

l

,