LD-88-047, Forwards Amend C to CESSAR-DC (Design Certification), Chapters 5,6 & 10.Summary of Significance of Revs Also Encl

Forwards Amend C to CESSAR-DC (Design Certification), Chapters 5,6 & 10.Summary of Significance of Revs Also Encl

ML20150B803
Person / Time
Site:	05000470
Issue date:	06/30/1988
From:	Scherer A ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
To:	Miraglia F NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM), Office of Nuclear Reactor Regulation
Shared Package
ML20150B805	List: LD-88-047, Forwards Amend C to CESSAR-DC (Design Certification), Chapters 5,6 & 10.Summary of Significance of Revs Also Encl ML20150B818
References
LD-88-047, LD-88-47, NUDOCS 8807120188
Download: ML20150B803 (11)

Text

,

= --

s i% . i

\

J }

p-CO BU5TidM ENGINEERING

s. f ,

' June 30,1988  ;

LD-88-047 IM i

i' ,

4 't I Docket No. STN 50-470F  ;

y ,, (Project No. 075) h i

Mr. Frank e. MiragPa

' Assopte Director for ')rojects j Gffice of Nuclear Reector Regulation  ;

, Attn: Document 76.4 trol Desk U. S, Nuclear Reg alatorj Commission

-t Washington, D.C. ' 20555 ' >

Subject:

Combustion Endneering Standard Safety Analyst. Report -

' Submittal Group C: Amendments to L'hapter 5, 6, and 10 ,

Dear R'. Miraglia:

q This letter ' transmits the next in Combustion Engineering's series of m modifications to the Combustion Engineering Standard Safety Analysic k^ Report - FSAR (CESSAR-F). Since the purpose of our modifications is to upgrade our current Final Design Approval (FDA-2) to a Design Certification, we refer to the ; mvised CESSAR-F as CESSAR-DC. A e. y in are aware, ?>.e enhanced and expanded design described in CESSAR-DC '

c will be called the System 80+U Standard Design.

i The enclos.ure to this letter provides you with our draft revisions to sections of Chapters 5, 6, and 10. Attachment (15 to this letter provides a management overview of the enclocd revisions. A summary of our view ,

of the significance of these revisfora is provided ici Attachment (2). ,

Revisions relt.tive h CEdSAR-F are identifico by a bar in the right-hand ma rg' n . . 'fo dist'.ngalsh the amer dments to CESSAR-F whi.;h are Lvnded i to lead to Oesign Certification from the amenlments made in the 'oarse of updat'ng CESSAK-F, we are urimg a lettereu amendnient system fc.' I CESSAWDC. This lettered amendmeat syatera was introduced in the submittal of Reference ( A). The enclosed revisions to Chaleiers 5, 6, and 10 are identified t.s Amendment 7

\

We hope to formal y submit a r.et of printed CESSAT'-DC vccumes to you in the near future. With that submittal, ne intend to formtlly rec uast opening of a separcte ducket for CESSAR-DC, as describeit in References 8007120100ADOCK 0000 080 m C'

_- PDR

" K '

Power Sy',1 > ns 1000 Prospect Hill Road (203) 688 1911 Combust an 4 ng neenng. Inc. Post O'fce Box 500 Tdex. 99297

1. ndsor. Connectet 06095wSOL U

y i; e ,

u  : h oE , Mr. F. J. Miraglia ,

- IU l LD-88-04N, i June 30,1988

,//

<! \ Page 2 X i l5 g

/

(B) and (C). The issue of the catego=y n3id limit of the fees to wtdeh we will be liable [ Reference (D)], however, ecntinues to remain an impediment to our submittal. We are appreciative phdt this matter has been taken under advisement and la being giveu perious consideration (Reference (E)]. We are hopeful that, .when this matter is talwn to the Commission, the result will be a sa+' %ctory resolution of our concerns, removing this impediment to our subn ll. In the meantime, however, we request that a means be found widch . sill protect our, rights and thus allow the technical review to proceed unencumbered. '

If we can be of any additional assistance in this, matterjlplease fal free to call me or Dr. Michael D. Green of my staff at (209 285'5204. 6 1

\',' ).

trul Vei y / \ y yot rs, q -)

COMBUSTIO!i ENGINEERINC,' !NC.

Mrecur NJelear Licensing /

AES:ss Attachments: As Stated .

/

Enclosure:

As Stated cc: Frank Ross (DOE - Germantown) / ,r .

A i

I h

Y i N 4

/

/

l

\

({,

d' l

l l

k l

l k

)

4

-, ,: - . x

{f \

LD-88-047

~

Mr. F. J. Miraglia;, j .

June 30,1988 ,

Page 3

,\ \ . iE$ r.

} ', ) M IInfeNnces: (A) Inttee, LD-88-026, A. E. - Scherer (C-E) to F. J. Miraglia (NRC), dated April 11, 1988.

' 3 ig - f ,1 1 , .

. ,)\q;A'. 'N 1  :,.

~

(B) Letter, LD-87-050, A. E. Scherer (C-E) to F. J. Miraglia (NRC). dated September 18, 1987.

. i (C) Letter, L. S. Rubenstein (NRC) to A. E. Scherer s jj/M..,il, (C-E), dated October 13, 1987.

T n

/ .f D) Letter, LD-88-009, A. E. Scherer (C-E) to 3

.. s L. W. Zech, Jr. (NRC), dated February 1,1988.

4 (E) Letter, V. Stello (NRC) to A. E. Scherer (C-E),

dateC. June 3,1988.

)

v, e ' .

\

.e li', y .s W

/s i /

I I

I 1

'l i

1 .

1 :s ( /s i

f i

l' l

y

• . . Attachm:nt (1) to LD-88-047 Page 1 of 2 Summary of Significant Revisions for CESSAR-DC, Amendment C*

Section 5.4.7 ("Residual Heat Removal System")

1. The design pressure of the Shutdown Cooling System (Residual Heat

• Removal System) was increased to a nominal value of 900 psig.

2. The Shutdov'n Cooling System (SCS) is designed so that the SCS pumps can be tested at full-flow conditions with the reactor operating at power.

3. The SCS pumps are functionally interchangeable with the Containment Spray pumps.

4. The SCS is designed to inject cooling water directly into the reactor vessel downcomer.

5. The need for post-LOCA recirculation changeover was eliminated by the new In-Containment Refueling Water Storage Tank.

Section 6.3 ("Emergency Core Cooling System")

1. The Emergency Core Cooling System, or Safety Injection System (SIS;, was revised to include four mechanically separate safety injection trains.

2. The SIS is designed to inject water directly into the reactor vessel downcomer.

3. The low-pressure safety injection pump function is no longer required to meet the criteria of Appendix K. (Ample capacity is provided by the high-pressure pumps and the safety injection tanks.)

l l

• These revisions correspond to the scope of Chapter 5 of the EPRI ALWR Requirements Document.

t

?

. . . Attachm2nt (1) to LD-88-047 Page 2 of 2

\

\

4. The SIS is designed so that the safety injection pumps can be tested '

at full-flow conditions with the reactor operating at power. '\

5. Tha SISg designed t'o perform the boron injection functim for safe -

shubi[wn and accident mitigation. #

P

6. An in-containment refueling water stoluge tank is now the source of water for the safety injection pumps.

Section 10.4.9 ("Emergency Feedwater Systen:"),

1. The Emergency Feedwater (EFW) System is now included in the design scope of the System 80+U Standard Design.

2. The EFW System features two (2) mechanically separate trains; r,Neh are used only for emergency operation (the EFW System has no auxiliary or plant startup function). Each EFW train includes a full-capacity, steam-driven pump and a full-capacity, motor-driven pump.

3. The EFW System is designed so that the EFW pumps can be tested at full-ficw conditions with the reactor operating at power.

4. The water source for the EFW pumps includes two (2) safety-grade storage tanks with a total capacity of 350,000 gallons.

Attachmsnt (2) to LD-88-047 Page 1 of 5

SUMMARY

OF CESSAR-DC DESIGN CHANGES FOR SUBMITTAL GROUP C (CHAPTERS Sp, 6p, AND 10p)

ITEM DESCRIPTION SECTIONS 1

0 Note: This Attachment addresses both All editorial and technical changes judged '

to be of some significance. Minor changes such as revised figure numbers are not addressed.

1 The design pressure of the Shutdown 5.4.7.1.2 Cooling System (SCS) was increased to a T:5.4.7-1 nominal value of 900 psig.

2 The low-pressure safety injection pumps are no longer used for SCS operation.

3 The SCS is designed so that the SCS 5.4.7.1.2.J pumps can be tested at full-flow conditions with the reactor operating at power.

4 The SCS pumps are functionally 5.4.7.1.2 interchangeable with the Containment 5.4.7.1.3.P Spray pumps.

5 The SCS is designed to inject cooling 5.4.7.2.1 water directly into the reactor vessel 5.4.7.2.2 downcomer.

6 Post-LOCA recirculation changeover has 5.4.7.1.1 been eliminated as a result of adding 5.4.7.1.3.M the in-containment refueling water 5.4.7.1.3.N storage tank.

7 The SCS heat exchangers are sized to 5.4.7.1.2 maintain a water temperature of 120 F 5.4.7.1.3.P at 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after shutdown. 5.4.7.2.2 5.4.7.2.5 5.4.7.3 T:5.4.7-1 T:5.4.7-2 T:5.4.7-4

. . AttachmOnt (2) to LD-88-047 Page 2 of 5

SUMMARY

OF CESSAR-DC DESIGN CHANGES FOR SUBMITTAL GROUP C (CHAPTERS 5p, 6p, AND 10p)

ITEM DESCRIPTION SECTIONS

, 8 The SCS interface requirements were 5.4.7.1.3 l updated to include Regulatory Guides

( 1.89, 1.97, and 1.148.

9 Technical data related to interlocks 5.4.7.1.1 l with the RCS and the initiation of SCS 5.4.7.1.2 operation were revised. These data will 5.4.7.2.1 x be supplied when the RCS performance 5.4.7.2.6 analyses are completed. 5.4.7.3 10 The SCS instrumentation will be 5.4.7.2.2.B described "LATER".

11 The SCS Failure Modes and Effects T:5.4.7-3 Analysis will be completed "LATER".

12 The Safety Injection System (SIS) was 6.3.1.1 revised to include four mechanically 6.3.2.1 separate trains. Data on SIS flow 6.3.2.2.4 distribution in the previously 6.3.2.5.2 shared-header system was deleted (the previous Table 6.3.2-4 was deleted).

13 The Ic'4-pressure safety injection putap 6.3.1.1 function is no longer required to meet 6.3.1.2 the criteria of Appendix K. Ample 6.3.1.3.A capacity is provided by the 6.3.1.3.M high-pressure pumps and the safety 6.3.1.3.N injection tanks. 6.3.2.2 6.3.2.5.2 6.3.2.5.4 T:6.3.2-1 14 The SIS is designed to perform the boron 6.3.1.1 injection function for safe shutdown and accident mitigation.

15 The SIS pumps are used along with the 6.3.1.1 Safety Depressurization System for 6.3.2.2.3 bleed-and-feed operations.

., , Attachmnnt (2) to LD-88-047 Page 3 of 5

SUMMARY

OF CESSAR-DC DESIGN CHANGES FOR SUBMITTAL GROUP C (CHAPTERS Sp, 6p, AND 10p)

ITEM DESCRIPTION SECTIONS 16 An in-containment refueling water 6.3.1.2 storage tank is now the source of water 6.3.1.3.A for the SIS pumps. Post-LOCA 6.3.1.3.C recirculation changeover is, therefore, 6.3.1.3.E no longer required. 6.3.1.3.J 6.3.1.3.L 6.3.1.3.M 6.3.2.1 6.3.2.2 6.3.2.5.2 6.3.2.5.4 6.3.2.7 T:6.3.2-1 T:6.3.2-3 T:6.3.2-4

. 17 The SIS is designed to inject water 6.3.1.2 directly into the reactor vessel 6.3.1.3.M downcomer. 6.3.2.2 6.3.2.5.4 18 The interface requirements were expanded 6.3.1.3.A to include additional General Design Criteria (#14,17,30,31,32,34, and 56) and Regulatory Guides (#1.45, 1.47, 1.68.2, 1.84, 1.85, 1.97, and 1.148). .

19 SIS flow is delivered to the reactor 6.3.1.3.A vessel within a maximum of 40 seconds after an initiation signal.

20 Setpoints for isolation of SIS and the 6.3.1.3.A interlock with the RCS will be provided 6.3.2.2 "LATER". 6.3.2.5.1 21 The SIS Failure Modes and Effects T:6.3.2-2 Analysis will be completed "LATER".

22 SCS Safety-Related Instrumentation will 6.3 be presented in Table 7.5-2 (the previous Table 6.3.2-3 was deleted).

Attachmsnt (2) to LD-88-047 Page 4 of 5

SUMMARY

OF CESSAR-DC DESIGN CHANGES FOR SUBMITTAL GROUP C (CHAPTERS 5p, 6p, AND 10p)

ITEM DESCRIPTION SECTIONS 23 The number and identification of SIS F:6.3.2-1A valves was revised (and previous Table F:6.3.2-1B 6.3.2-6 Nas deleted).

24 A requirement has been added for 6.3.1.3.K post-accident monitoring of the SIS.

25 The SIS is designed so that the SI pumps 6.3.1.2.1.D can be tested at full-flow conditions with the reactor operating at power.

26 The Emergency Feedwater (EFW) System is 10.4.9 now included-in the scope of supply for the System 80+ Standard Design.

27 The EFW System contains two mechanically 10.4.9.1.1 separate trains which are dedicated to 10.4.9.1.2 emergency use. 10.4.9.2.3 10.4.9.2.2.5 10.4.9.2.3 10.4.9.2.4 10.4.9.3 28 Each EFW train includes a full-capacity, 10.4.9.1.2.A steam-driven pump and a full-capacity, 10.4.9.1.2.G motor-driven pump. Each of these pumps 10.4.9.2.1 has a capacity of 500 gpm, sufficient to 10.4.9.2.2.1 meet emergency needs. 10.4.9.2.2.2 10.4.9.3 29 The EFW system is designed so that the 10.4.9.4.2 EFW pumps can be tested at full-flow conditions with the reactor operating at I power.

30 The water sourca for the EFW pumps 10.4.9.1.2.J includes two storage tanks with a total 10.4.9.2.1 capacity of 350,000 gallons. 10.4.9.2.2.3 10.4.9.3 l

l l

[

l l

. Attachment (2) to LD-88-047 Page 5 of 5

SUMMARY

OF CESSAR-DC DESIGN CHANGES FOR SUBMITTAL GROUP C (CHAPTERS Sp, 6p, AND 10p) ,

ITEM DESCRIPTION SECTIONS 31 The EFW System is designed to deliver 10.4.9.1.2.F flow to the steam generators within 60 seconds of an initiating signal.

32 The EFW System is designed as a 10.4.9.1.1 safety-grade ystem. It can be operated 10.4.9.1.2 either manually or automatically. 10.4.9.2.1 T:10.4.9-1 10.4.9.2.2 10.4.9.2.3 10.4.9.2.4 T:10.4.9-3 l

l l

l'

CESSAR !!!!inemen l

l HfTING OF AMENDMENTS Amendment No. Date A September 11, 1987 B March 31, 1988 C June 30, 1988 i

i l

l l

1 I

l l

l l

l l Amendment C l June 30, 1988 l