LD-88-026, Forwards Draft Revs to C-E Chapters 1,4,5 & 9 to C-E Std Sar.Meeting to Resolve Issues Re Schedule & Composition of Submittals as Part of Draft Licensing Review Bases & Related Issues,Requested

Forwards Draft Revs to C-E Chapters 1,4,5 & 9 to C-E Std Sar.Meeting to Resolve Issues Re Schedule & Composition of Submittals as Part of Draft Licensing Review Bases & Related Issues,Requested

ML20151H795
Person / Time
Site:	05000470
Issue date:	04/11/1988
From:	Scherer A ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
To:	Miraglia F Office of Nuclear Reactor Regulation
Shared Package
ML20151H797	List: LD-88-026, Forwards Draft Revs to C-E Chapters 1,4,5 & 9 to C-E Std Sar.Meeting to Resolve Issues Re Schedule & Composition of Submittals as Part of Draft Licensing Review Bases & Related Issues,Requested ML20151H819
References
LD-88-026, LD-88-26, NUDOCS 8804200529
Download: ML20151H795 (18)

Text

COMBUSTION ENGINEERING April 11,1988 LD-88-026 Docket No. STN 50-470F (Project No. 675)

Mr. Frank J. Miraglia Associate Director for Projects Office of Nuclear Reactor Regulation Attn:

Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Combustion Engineering Standard Safety Analysis Report -

Submittal Group B:

Amendments to Chapters 1, 4, 5, and 9

Dear Mr. Miraglia:

This letter transmits the next in Combustion Engineering's series of modifications to the Combustion Engineering Standard Safety Analysis 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 revised CESSAR-F as CESSAR-DC.

As you are aware, the enhanced and expanded design described la CESSAR-DC will be called the System 80+m Standard Design.

The enclosure to this letter provides you with our draft revisions to Chapters 1, 4, 5, and 9.

Attachment (1) to this letter provides a management overview of the enclosed revisions.

A summary of our view of the significance of these revisions is provided in Attachment (2).

Revisions relative to CESSAR-F are identified by a bar in the right-hand margin.

To distinguish the amendments to CESSAR-F which are intended to lead to Design Certification from the amendments made in the course of updating CESSAR-F, we are introducing a lettered amendment system for CESSAR-DC.

Revisions to Chapter 1 which were submitted previously as Amendment 12 [ Reference ( A)] are now identified as Amendment A.

New revisions to Chapter 1, 4, 5, and 9 are identified as Amendment B.

We hope to formally submit a set of printed CESSAR-DC volumes to you in the near future. With that submittal, we intend to formally request opening of a separate docket for CESSAR-DC, as described in References 9

8804200529 000411 g j PDR ADOCK 0500 0

K Power Systems 1000 Prospect H,Il Road (203) 68B-1911 6. g $

Combustion Engineenng. Inc.

Post Offce Box 500 Te!ex 99297 3 Windsor, Connectcut 06091 0500 v

Mr. F. J. Miraglio LD-88-026 April 11,1988 Page 2 (B) and (C). The issue of the category and limit of the fees to which we will be liable (Reference (D)), however, continues to remain an impediment to our submittal.

We request, therefore, that the issue be addressed in a timely manner or a means be found which will protect our rights and thus allow the technical review to proceed unencumbered.

As a result of recent feedback from your staff and our experience to date, we have initiated a review of the schedule and composition of the submit-tais in our draft Licensing Review Bases [ Reference (E)).

The purpose of our review is to develop more realistic submittal dates and logical submittal groups which will facilitate an efficient review.

As an initial result of our review, we have revised the submittal date for Group C to June 30, 1988.

In order to ensure that the results of the review meet our mutual objec-tives, we intend to review our proposed submittal groups and schedule with your staff before finalizing them.

We believe that the most effective approach will be to have a meeting with your staff in the near future to resolve this as well as other issues delaying the Licensing Review Bases agreement.

If we can be of any additional assistance in this matter, please feel free to call me or Dr. Michael D. Green of my staff at (203) 285-5204.

Very truly yours, COMBUSTION ENGINEERING, INC.

Director Nuclear Licensing AES:ss Attachments:

As Stated

Enclosure:

As Stated I

Mr. F. J. Miraglia LD-88-026 April 11,1988 Page 3 l

References:

(A) Letter, LD-87-054, A. E. Scherer (C-E) to F. J.

Miraglia (NRC), dated September 18, 1987 l

(B) Letter, LD-87-050, A. E. Scherer (C-E) to F. J.

Miraglia (NRC), dated September 18, 1987 (C) Letter, L. S. Rubenstein (NRC) to A. E. Scherer, I

(C-E) dated October 13, 1987 (D) Letter, LD-88-009, A. E. Scherer (C-E) to L. W.

Zech, Jr. (NRC), dated February 1,1988 (E) Letter, LD-88-005, A. E. Scherer (C-E) to F. J.

Miraglia (NRC), dated January 19, 1988 l

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Att:chment (1) to LD-88-026 Page 1 of 2 l

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Summary of Significant Revisions for CESSAR-DC Amendment Il Chapter 1 1.

Sections 1.1 and 1.2 were updated to reflect current terminology and design overview.

Commitment to the NRC Standardization, Safety Goal, and Severe Accident Policies is stated.

2.

Responses to NRC questions were incorporated (see C-E Letters LD-88-019 and LD-88-020 dated March 18, 1988).

3.

The Instrumentation and Control Room design summaries in Section 1.2 were updated.

4.

The list of C-E topical reports incorporated by reference (Section 1.6) was updated, 5.

The list of Regulatory Guides in Table 1.8-1 was expanded to include those from CESSAR-F, Appendix A.

Chapter 4 1.

The number of Control Element Assemblies (CEAs) was increased from 89 to 93.

Eight four-element, full-strength CEAs and the thirteen part-length CEAs were replaced by 25 full-length part-strength CEAs.

2.

Ifafnium was added as an absorber material in four-element CEAs.

3.

Gadolinia was added as an option for burnable poison rods.

Combustion Engineering has submitted a Topical Report on this modification.

4.

The description of fuel-related demonstration programs was updated.

5.

The thermal-hydraulic methodology was updated to include statistical combination of uncertainties. This methodology has been accepted by the NRC for reload analyses.

6.

The neutronics methodology was updated to reflect revised methods.

The corresponding Topical Report has been approved by the MRC.

7.

The hot leg temperature was decreased to 615 F.

Chapter 5 1.

The introduction was revised to correspond to the System 80+

Standard Design.

(Additional data and information will be provided in Submittal Groups C and D.)

Attachment (1) to LD-88-026 i

Page 2 of 2 2.

The Pressurizer volume was increased.

l 3.

The Steam Generator heat transfer area and secondary-side water volume were increased, f

4.

Materials and ASME Code compliance information in Section 5.2 was updated.

(Overpressure protection information and analysis will be provided in Submittal Groups C and D.)

5.

Section 5.3 was updated to reflect a 60 year design life for the 1

I reactor vessel.

(Additional revisions will be provided in Submittal Groups C and D.)

6.

The reactor coolant system description in Section 5.4 was updated to reflect System 80+ current information.

(Additional information will be provided in Submittal Groups C and D.)

4 Chapter 9 1.

Standardized Functional Descriptions for the Demineralized Water Makeup and Condensate Storage Systems were added to Section 9.2.

l 2.

A Standardized Functional Description for the Process Sampling System was added to Section 9.3.

3.

The Chemical and Volume Control System design was revised to reflect reliability improvements and to reflect the transfer of accident mitigation and safe shutdown functions to other, safety-grade systems.

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Attachacnt (2) to LD-88-026 Page 1 of 13

SUMMARY

OF CESSAR-DC DESIGN CHANGES FOR SUBMITTAL GROUP B (CHAPTERS 1, 4,

Sp, AND 9p)

ITEM DESCRIPTION SECTIONS Note: This Attachment addressus both editorial and technical changes judged 3

to be of some significance.

Minor changes such as revised figure numbers are not addressed.

1 1

The "Contents of Report" was revised to Contents of identify the CESSAR-DC appendices which Report will summarize compliance with the Severe Accident Policy Statement.

(These appendices are also identified in Section 1.1.3.4.)

2 CESSAR-DC's compliance with the NRC's 1.1, 1.1.1, Severe Accident, Safety Goal, and 1.1.3.4 i

Standardization Policies was stated.

i 3

The summary of the System 80+TM Standard 1.1.1, 1.1.2, i

Design was revised for clarity.

(There 1.1.5, 1.2, were, however, no significant changes.)

1.2.1, 1.2.2, 1.2.3, 1.2.4, 1.2.5 4

The Chemical and Volume Control System 1.1.3.2, (CVCS) was removed from the description 1.2.11.2 of safety system functions in response to NRC Question 281-1 (C-E Letter LD-88-019, 3/18/88).

5 The description of interfaces was 1.1.3.3 replaced with the summary of Standardized Functional Descriptions from the draft Licensing Review Basis document.

6 The reactor core design criterion on 1.2.3.1 departure from nucleate boiling was revised for consistency with Chapter 4.

(This change did not affect the safety 1

analysis.)

7 The Containment System description was 1.2.4.1, revised and the Containment Spray System 1.2.4.5, description was added as a result of NRC T:1.2-1 Question 281-4.

AttcchOnt (2) to LD-88-026 Page 2 of 13

SUMMARY

OF CESSAR-DC DESIGN CHANGES FOR SUBMITTAL GROUP B (CHAPTERS 1, 4,

5p, AND 9p)

ITEM DESCRIPTION SECTIONS 8

The summaries of Instrumentation and 1.2.5, Control Systems and the Nuplex 80+TM 1.2.5.1.2, Control Complex were revised to more 1.2.5.1.4, completely summarize the current design.

1.2.5.1.6, 1.2.6, T:1.2-1, T:1.3-4, 1.7 9

In anticipation of a future submittal, 1.2.10.2 Section 1.2.10.2 states that Standardized Functional Descriptions for Fuel Storage are provided in Section 9.1.

(Section 9.1 will be included in Submittal Group E.)

10 A reference to chapters on Physical 1.2.13 Plant Security was added in response to NRC Question 500.2 (C-E Letter LD-88-020, 3/18/88).

11 In anti":ipation of a future submittal, 1.2.13 Section 1.2.13 states that Standardized Functional Descriptions and design features for Physical Plant Security are provided in Chapters 2, 3,

8, 9 and 13.

(This material will be in Submittal Groups D and E.)

12 The Safety Depressurization System was T:1.2-2

-dded in response to NRC Question 281-2 (C-E Letter LD-88-019, 3/18/88).

This system will be located in Section 6.7, however, not Section 5.4.12 as indicated in the response to the question.

13 Responses to NRC Questions 281-1 and T:1.2-2 281-2 idicated that the CVCS would be removed from Table 1.2-2, since the CVCS l

is not required for accident mitigation.

The CVCS will have interfaces with other systems and, thus, remains in Table 1.2-2, 14 The comparison of reactor T:1.3-1 characteristics was revised to reflect the information in the revisions to Chapters 4 and 5.

e Attcchm nt (2) i to LD-88-026 Page 3 of 13 i

SUMMARY

OF CESSAR-DC DESIGN CHANGES i

FOR SUBMITTAL GROUP B (CHAPTERS 1, 4,

Sp, AND 9p)

ITEM DESCRIPTION SECTIONS I

l i

15 Topical Reports referenced in Chapters 4 1.6 i

and 5 were added.

The material already l

listed was also updated to reflect the current status.

Report CENPD-132-P was added for consistency with Table 1.5-1.

16 The list of applicable Regulatory Guides 1.8, T:1.8-1 was revised to include information from r

CESSAR-F, Appendix A and Regulatory f

Guides referenced in Chapters 4 and 5.

Regulatory Guides withdrawn by NRC were i

also identified.

17 Section 1.9 of CESSAR-F (Anticipated 1.9 Transients Without Scram) was deleted in Amendment A as a result of design 1

revisions.

Amendment B includes an i

appropriately marked page in place of i

the previous Section 1.9 to clearly indicate its deletion.

18 The total number of CEAs was increased 4.1, 4.2.2.4, from 89 to 93.

Eight full-length, T 4.2-1, L

I full-strength and 13 part-length, 4.3.2.2.1, full-strength CEAs were removed.

4.3.2.2.3, Twenty-five full-length, part-strength 4.3.2.2.5.3, j

CEAs were added to improve power +

4.3.2.2.5, j

maneuvering.

4.3.2.4.2, i

4.3.2.4.3.4, 4.3.2.4.4, 4.3.2.5,

+

4.3.2.7.3.3, 4.3.2.7.4, a

j 4.3.2.7.5.2, 4.4.4.3, 19 Figure 4.2-1, Reactor Core Cross 4.1 Section, was added for consistency with 1

the existing text.

(This is a l

description change only, not a design 1

change.)

20 The transients which were previously 4.2.1.1 included in the analysis of a fuel I

assembly's compliance with design basgs were explicitly listed in CESSAR-DC.

)

(This is an editorial change only.)

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Attcchment (2) y4 to LD-88-026" j

Page 4 of 13' SUMMANY OF CESSAR-DC DESIGN CHANGES

! FOR SUBMITTAL GROUP B i

(OHAPTERS 1, 4,

Sp, AND 9p; r

ITEM DESCRIPTION SECTIO S a

21 In the manufacture of the CEA guide 4.2.1.1.3, tubes and Zircaloy strip stock, limits 4.2.1.1.5 were placed on mechanical properties.

a (These changes enhance performance.)

1 22 The description of fuel assembly design 4.2.1.1.3, 1

bases was expanded to list a limit on 4.2.1.1.4, carbon conte'nt in Zircoloy.

4.2.1.1.5, 4.2.1.2.2.4,'

4.2.1.2.3.1 t

23 Additional description of the 4.2.1.1.6 manufacturing process for stainless steel castings was provided.

(This change did not affect the design or

-j performance but was provided for i

completeness.)

l.

24 Additional detail was provided'on the 4.2.1 '1.9 1

manufacture of Inconel spacer grid strips.

(This change did not affect the i

design or analysis.)

i 25 Material procurement and fa*tication 4.

.1.1.4, standards were updated.

aterial 4.2.1.1.6, performance and applica' so remained 4.2.1.1.7, i

unaffected.)

4.2.1.1.8, i

4.2.1.1.9, 4.2.1.2.2.3, 4.2.1.2.3.2, 4.2.5 1

26 The description of fuel pellet chemical 4. 2,.1. 2. 4.1 analysis was updated.

(There were no t

changes in the analysis results.)

27 The method of evaluating the effects of 4.2.1.2.4.3, irradiation on fuel pellot density was 4.2.3.2.8 1

updated to reflect current practice.

j (This is consistent with NRC guidance i

and our approved model.)

28 Gadolinia-Urania was added as ani 4.2.i.3, l

alternative option to the B4C-AUJ03 4.2.1.3.4, absorber in the burnable poison rods.

4.2.2.3, l

I (This application of gadolinia is being 4.2.3.3.1, reviewed by the NRC in Combustion 4.2.3.3.2, i

Engineering's Topice.1 Report 4.2.4.3.1, CENPD-275-P.)

1.3.4.3.2 l

l

-,,, - l

4 4

l Atttchm nt-(2) a ho LD-88-026 j

Page'5 of 17 t

SUMMARY

OF CESSAR-DC DESIGN CHANGES FOR SUBMITTAL GROUP B (CHAPTERS 1,',4, Sp, AND 9p) l 3

i ITEM DESCRIPTION SECTIONS l

9 i

29 The B4C absorbar in the 4-element, 4.2.1.4.1, full-length CEAs is replaced with 4.2.1.4.2, a

hafnium in order to extend the CEA 4.2.1.4.4, design life from 10 to 20 years.

4.2.2.4, 4.2.3.4, r

c L

4.2.4.4, Tt4.2-1 30 The fuel assembly hold-down spring 4.2.2.1 l

diameter was changed from l'.656 in, to 1.859 in. and the wire diameter was increased from 0.316 in to 0.319 in.

c (These reviulons did not affect the safety analysis.)

i i

31 The description of the contact between 4.2,2.1 j

the fuel assembly hold-down springs and the upper guide structure was revised to be more complate.

(Fuel assembly performance was unaffected.)

32 Minor improvenants in the manufacture of 4.2.2.1, the lower and of the fuel assemblies 4.2.4.1.1 wore described.

(Fuel assembly performance was unaf fected. )

33 Minor changes were made to the 4.2.2.1 I

description of fuel assembly guide tube j

stability.

(Fuel assembly performance j

was unaffected.)

34 Minor changes were.made to the 4.2.3.1.1, description of fuel'assenbly analyses.

4.2.3.1.2, (Fuel assembly performance was 4.2.3.1.3, unaffected.)

4.2.3.2.1, 4.2.3.2.4

)

35 For fuel design evaluation, a statement 4.2.3.1.2 that the OBE is equivalent to one-half i

SSE was deleted.

(10 CFR 100, Appendix j

A, provides this definition.

The j

analysis was performed jn conformance j

with the regulatien.)

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' i Attachmrt) # \\'

3 to LD ;GL -026 i

Page '6 of 13

..t e

x, i

.c N10fARY of CESSAR-DC QESIGN CHANGEF,

.(

I 'E.1, '

/ FOR SUDMITTAL GROUP B I,

'(/ I '

(CHAPTERS 1, 4,

Sp,' AND l'p) t<

/

DESCRIPTibN ITEM SECTIONS

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.. j 36 ANO-2 (System-80R' fuel) was/ added to the 4.2.1.1.3 list of reactors which have not shown

'l significant bowing of fact-roda.

(This

[

)'

provides additional confidence in the 4

i o

fuel rod design.)

N*'

~

Descriptions of fuel rod internal 4. 2. 3. 2. 3 ( C ) ',

s idriding and chemical reacticos we:{e

- 4.2.3.2.3(E) dsed to be more complete.

(The A sign anaIysis remained unchangt<.t{)

I

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,i 3G description of the results if 4.2.3.2.4 exam 16ations forIfu l rod fretting was

'\\! (\\

revised for compldteness.

(The design i

and analysis were ux:: hanged.)

/ \\

)

/

The description of f'uel dimensional 4.2.3J2.8 39 4,

stability was updated to reflect more recent results.

(The conclusions remaine'.D the same.)

1

)

)

40 The description of participation in tha 4.2.3.2.10(I)

/

Halden experimental; program was updated.

(There was no impitt on fuel design or

.I ana7ysis.)

)

4

)

di Descriptions c.7 fuel-related inspection 4.2.1.5.1, programs and Eknerience were updated.

4.2.3.2.10(C),/,

(Results have v Yri'f.ed acceptable fuel h 2.3.2.10(D,

,ji 4. 2. 3. 2.1o { 3 )(',

performance.)

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(

)

4. 21. 3. 2.10 ( K),

/ '>

T:4)2 3 4

h 1

1 v

,1 1

42 Regulatory Guides 1.46, 1.48, and 1.51 4. J /. 5 were deleted from the.*]/st ol'r'elevant Regulatory Guides for raz'ctol -

't interfaces.

(The.y'werekith6hawnbythe NRC.)

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43 The requirement on maximu6' enrichment

4. 2. 5 ( D) for new fuel storagrjraaks was increased from 3.7 w/o U-235 yo 4. 3 'w/o.

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s 44 The description of' power distribution 4.3.2.2.1 men,jtoring was, expanded t,Andicate the

/

use of Core Prcf.ection Calculators.

I (This is an editorial change only.)

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e, Attachment (2) j to LD-88-026 lg 3

Page 7 of 13 K

O I

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/

SUMMARY

OF CESSAR-DC DESIGN CHANGES

,i j

FOR SUBMITTAL GROUP B i

(CHAPTERS 1, 4,

Sp, AND 9p)

(>.

'i 8

' ITEM DESCRIPTION SECTIONS j

'I<-

3 1

Appro'ed methodology for the statistical T:1.3-1, 45 N (-

v

'/

cambination of uncertainties was 4.3.2.2.2,

)

vi described for reactor core thermal 4.3.2.2.4, 3

margin unalysis. [This change resulted 4.4.1.1,

/

in % thermal margin estimate of 15%

4.4.2.2.1, (idereas'd from 10%).)

4.4.2.2.2,

' f

4. 4. 2. 2. 2. 2 (D),

4.4.2.8, 4.4.2.9.4,

)'

4.4.2.9.5, J

4.4.2.10, 4.4.4.1, 4.4.4.5.2, s

,\\

1 T:4.4-2 e

46, Tha methodology for analyzing load 4.3.2.2.3, following capabilities was revised. (The 4.3.3.1.1.4 ysafety analyses were unaffected.)

47 The hRC-approved DIT, ROCS and MC codes 4.3.2.3, were csed for calculation of neutron 4.3.2.3.3,

' cross sections, coarse-mesh, and 4.3.3.1, fine-mosh power distributions.

(This 4.3.3.1.1, strearalined the analysis.

4.3.3.1.2.2.1, e'

T:4.3-15

. 48 The average void fraction was decreased 4.3.2.3.6, f

as a result of a 60 F reduction in hot 4.4.2.4 leg temperature, from 6210 F to 615 F.

49 Conservative CEA shutdown worths were 4.3.2.4.3, provided for the end of Cycle One,-

4.3.2.4.3.6 rather than for the end of an I,

equilibrium cycle because for the fuel management presented, the end of Cycle

,One has the lowest shutdown worth.

I 50

.CEA reactivity allowances were revised 4.3.2.4.3, slightly, reflecting design methociology 4.3.2.4.3.1, changes.

4.3.2.4.3.6 51

. The maximum neutron fluence predicted 4.3.2.8, for the reactor vessel was increased to 4.3.3.3, 6.0 X 10 (19) n/cm2.

(This resulted 5.3.1.4 from increasing the design life of the

<L reactor vessel to 60 years and using a larger uncertainty factor in the fluence predictions.)

k

Atttchm nt (2) to LD-88-026 Page 8 of 13

SUMMARY

OF CESSAR-DC DESIGN CHANGES FOR SUBMITTAL GROUP B (CHAPTERS 1, 4,

Sp, AND 9p)

ITEM DESCRIPTION SECTIONS 52 The reactor outlet full-power average T:1.3-1, coolant temperature was lowered 60 F to 4.3.3.1.1.4, 6150F to increase the reactor core T:4.4-1, thermal margin.

The cold leg T:4.4-4, temperature was correspondingly reduced T:4.4-9, from 5650F to 558 F.

5.1.4(G.10),

5.1.4(0.7),

5.4.2.1, T:5.1.1-1, T:5.1.1-2, T:5.4.2-1 53 The heat flux augmentation factor was 4.4.2.2.2.1(E),

removed since modern manufacturing

[4.3.3.4 was procedures have effectively precluded deleted) fuel pellet densification.

54 An explicit requirement to meet the 4.4.3.1.1 Safety Injection System net positive suction head criteria of Section 6.3 was added.

55 Appendix A of CESSAR-F (QUIX computer 1.5.2.3, code description) was deleted.

In T:1.5-1, CESSAR-DC the QUIX Manual is Reference Appendices 4A 4.3(14).

Appendices 4B and 4C were and 4B re-lettered to 4A and 4B in CESSAR-DC.

(These revisions are editorial.)

56 The pressurizer volume was increased to T:4.4-8, improve the response of the reactor T:4.4-9, 5.1.1, coolant system to transients.

T:5.1.1-2, T:5.1.1-3, T:5.1.4-3, T:5.4.10-1 57 The steam ge'.:erator size was increased T:1.3-1, to accomodate a larger number of tubes, T:4.4-8, an increased water volume, lower T:4.4-9, 5.1.1, pressure, and lower hot leg temperature.

T:5.1.4-2, (These changes were made to improve the T:5.1.4-3, reactor coolant system's response to T:5.1.1-2, transients.)

T:5.1.1-3, T:5.4.2-1, 5.1.4(0.7)

Attachm:nt (2) to LD-88-026 Page 9 of 13

SUMMARY

OF CESSAR-DC DESIGN LdANGES FOR SUBMITTAL GROUP B (CHAPTERS 1, 4,

Sp, AND 9p)

ITEM DESCRIPTION SECTIONS l

58 Discharge from the Reactor Coolant 5.1, 5.1.4(0.2)

System safety valves and the new motor-operated Safety Depressurization System valves was routed to the in-containment refueling water storage tank.

(This improves the quenching capability.)

59 The reference for definition of the 5.1.2, 5.2 reactor coolant pressure boundary was updated to ANSI 51.1 - 1983.

(This revision did not materially affect the System 80+ Standard Design.)

60 The list of Regulatory Guides applicable 5.1.4 to the design of the reactor coolant system was updated.

61 The set of guidelines for implementing 5.1.4(F.6, F.7) interface criteria for the emergency feedwater system was updated to ANS 58.9

- 1981.

62 Interface requirements for main steam 5.1. 4 ( F) isolation valve bypass and atmospheric dump valve control circuits were deleted.

(They are included in the scope of Chapter 7.)

63 The interface requirement on emergency 5.1. 4 ( F),

feedwater system unavailability was 5.1.4(G) deleted.

(This system is included in the System 80+ design scope, Chapters 7 and 10.

64 The interface requirements for 5.1.4(G) atmospheric dump valve control and actuation were deleted.

(Information is either included in Chapter 10 or is included in the scope of Chapter 7.)

The interface requirement on secondary 5.1. 4 (H) 65 side valve monitoring was deleted.

(It is included in the scope of Chapter 7.)

Atttchm nt (2) to LD-88-026 Page 10 of 13

SUMMARY

OF CESSAR-DC DESIGN CHANGES FOR SUBMITTAL GROUP B (CHAPTERS 1, 4,

Sp, AND 9p)

ITEM DESCRIPTION SECTIONS 66 Interface requirements on valve controls 5.1.4(I) were deleted.

(They are included in the scope of Chapter 7.)

t 67 The uncertainty on feedwater temperature 5.1.4(H.4) measurement was increased from 1 F to

5. 50 F.

(This change does not affect the design or analysis.)

1 68 Additional detail on the pressurizer 5.1.4(M.1, M.2) surge line was provided to avoid water

{

traps.

(This improved performance of the RCS and did not affect existing safety analysis conclusions.)

j 69 The requirement on system arrangements 5.1.4(M.4) for avoidance of reactor vessel cavity flooding was revised to include the Safety Injection System.

70 Additional requirements on the 5.1.4(M.20/21) pressurizer spray line were provided to minimize the potential for waterhammer.

71 A requirement was added to disallow loop 5.1.4(M.22) seals in the safety valve inlets.

72 Heat loads from steam generator supports T:5.1.4-2 were updated.

(Safety-related aspects of the design were unaffected.)

73 Regulatory Guide 1.147 was referenced 5.2.1.2 for determining ASME Code Cases in addition to the previously referenced Regulatory Guides 1.84 and 1.85.

74 Primary safety valve blowdown was 5.2.2.4, revised from 5% to 18.5%, consistent T:5.4.13-1 with previously approved experimental and safety analysis results (Appendix 5A).

75 The title was revised to include 5.2.2.10.1.4 standard IEEE-279.

(This was an editorial change only.)

Attcchm nt (2) to LD-88-026 Page 11 of 13

SUMMARY

OF CESSAR-DC DESIGN CHANGES FOR SUBMITTAL GROUP B (CHAPTERS 1, 4,

Sp, AND 9p)

ITEM DESCRIPTION SECTIONS 76 The reactor vessel material type was 5.2.3.1, changed from SA-533B (plate material) to T:5.2-2, SA-508 (forging material).

(This will 5.2.3.3.2.1, eliminate longitudinal welds in the 5.3.1.6.1, active core region and help increase 5.3.1.6.4.1, reactor vessel design life to 60 years.)

5.3.2.1 77 A requirement was added to restrict the 5.2.3.2.2 use of material containing cobalt in reactor coolant pressure boundary materials.

(This will reduce coolant contamination due to activated cobalt.)

78 The limitation on the extent of Reactor 5.2.3.2.3 Coolant Pressure Boundary insulation provided was removed.

79 The ASME Code was referenced, in place 5.2.3.4.2.1 of AWSA.S.4, for the current manufacturing process used to minimize hot cracking during welding.

80 The access to reactor vessel inlet 5.2.4.1 nozzles for inspections was described.

(This is an editorial change only.)

81 The reactor vessel head and beltline 5.2.3.1, region manufacturing method was changed 5.3.1.2 to a forging method.

(This will eliminate longitudinal welds in the active core region and help extend the reactor vessel lifetime to 60 years.)

82 Regulatory Guide 1.99 was referenced for 5.3.1.4 predictions of reactor vessel irradiation. (This is consistent with NRC guidance.)

83 The ASTM Standard reference for reactor 5.3.1.6, vessel surveillance was updated to the 4.3.1.6.2.1, 1982 version.

5.3.3.7 84 Neptunium was added as a candidate 5.3.1.6.4.1, material for neutron threshold T:5.3-5 detectors.

Attachmsnt (2) to LD-88-026 Page 12 of 13

SUMMARY

OF CESSAR-DC DESIGN CHANGES FOR SUBMITTAL GROUP B (CHAPTERS 1, 4,

Sp, AND 9p)

ITEM DESCRIPTION SECTIONS 85 The design basis of the Steam Generators 5.4.2.1 was revised to include an increased number of design transient cycles.

86 The description of reactor coolant pump 5.4.1.4 tests was revised.

(Pump test program conclusions are unaffected.)

87 Main Steam Isolation Valve and Main 5.1.4(I.3,I.6),

Feedwater Isolation Valve closure times 5.4.5.3 were revised from 4.6 seconds to 5 seconds.

(This change does rot affect the safety analysis conclusico.s. )

88 The design basis of the pressurizer was 5.4.10.1 modified to improve plant response during transients.

89 The thermal sleeves were removed from 5.4.10.2 the pressurizer surge and spray nozzles.

(This change was based on operating plant experience.)

90 Minor revisions were made to the 5.4.10.2 description of pressurizer level control.

91 Leak-Before-Dreak methodology was 5.1. 4 (C.1),

applied to reactor coolant system branch 5.4.14 lines, in accordance with recent revisions to General Design Criterion 4.

i 92 A Standardized Functional Description 9.2.3 was provided for the Demineralized Water Makeup System.

I 93 An editorial revision was made to 9.2.1, 9.2.2, indicate that Standardized Functional 9.2.4, 9.2.5 Descriptions would be provided later for the Station Service Water System, Cooling System for Reactor Auxiliaries, Potable and Sanitary Water Systems and the Ultimate Heat Sink.

Atte.chmtnt (2) to LD-88-026 Page 13 of 13 SUFMARY OF CESSAR-DC DESIGN CHANGES

OR SUBMITTAL GROUP B

' 'FDS 1, 4,

Sp, AND 9p)

ITEM DESCRIPTION SECTIONS 94 An editorial revision was made to 9.3.1, 9.3.3, indicate that Standardized Functional 9.4 Descriptions would be provided later for the Compressed Air Systems, Equipment and Floor Drainage System, and the Air Conditioning, Heating, Cooling, and Ventilation Systems.

95 A Standardized Functional Description 9.2.6 was provided for the Condensate Storage System.

96 A btandardized Functional Description 9.3.2 was provided for the Process Sampling System.

97 The Chemical and Volume Control System T:4.6-1, design w&s revised.

(It is no longer 9.3.4.1.1, required to perform any accident 9.2.4.1.2, mitigation or safe shutdown functions.)

9.3.4.1.3, 9.3.4.2, 9.3.4.3, 9.3.4.3.7 98 The CVCS design was revised to include 9.3.4.1.2, two charging pumps, not three.

(The 9.3.4.1.3, CVCS is no longer required to perform 9.3.4.3.1 any accident mitigation or safe shutdown functions.)

99 Modifications were made to the CVCS 9.3.4.1, which improve reliablity.

9.3.4.2, 9.3.4.3, 9.3.4.5 100 Makeup and chemistry control of the 9.3.4.1.1, water in the in-containment refueling 9.3.4.2.1, water storage tank were added to the 9.3.4.2.3 list of CVCS functions.