LD-83-044, Forwards Amend 8 to CESSAR-F.List of Rev Topics Encl

Forwards Amend 8 to CESSAR-F.List of Rev Topics Encl

ML20074A087
Person / Time
Site:	05000470
Issue date:	05/10/1983
From:	Scherer A ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
To:	Thomas C Office of Nuclear Reactor Regulation
Shared Package
ML20074A088	List: LD-83-044, Forwards Amend 8 to CESSAR-F.List of Rev Topics Encl
References
LD-83-044, LD-83-44, NUDOCS 8305120120
Download: ML20074A087 (5)

Text

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C-E Po*st Sy:ttm2 Tel 203/688-1911 Combustron Engincem.g irc Telex 99297 1000 Prospect Hill Road Windsor. Connecticut 06095 POWER SYSTEMS Docket No. STN-50-470F May 10,1983 LD 044 Mr. Cecil Thomas, Branch Chief Standardization and Special Projects Branch Office of Nuclear Regulatory Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

CESSAR-F Amendment Nunber 8

Dear Mr. Thomas:

Combustion Engineering, Inc., hereby submits for your review seventy (70) copies of Amendment No. 8 (non-proprietary) to CESSAR-F. A draft copy of this amendment has been supplied to the Staff for advance review.

The attached list provides a description of and explanation for the changes to each amended Section of CESSAR-F. A significant portion of the changes result from our responses to Open and Confirmatory items and have previously been '

submitted to the Staf f. These items are identified by reference in the attached list.

If we can be of any further assistance, please contact either myself or Mr. G.

A. Davis of my staff at (203) 688-1911, extension 2803.

Very truly yours, COMB Nr ING, INC.

eme

. E. eTer Director Nuclear Licensing AES:las Attachment cc: G. Meyer ()Og' F72100 1 8305120120 830510 PDR ADOCK 05000470 B PDR

Mr. C. Thomas LD Attachment Page 1 AMENDMENT NUMBER 8 TOPICS OF REVISION

1) CESSAR-F Scope and Interfaces (Chapter 1)

Revised to correct a typographical error identified during the Staff's review of the tabulation of reactor fuel design characteristics.

2) Classification of Components and Component Testing (Chapter 3)

Reference (2-1): Letter LD-83-018, A. E. Scherer to D. G. Eisenhut, dated February 28, 1983 Revised commitment to provide load limiting device test results on CESSAR-F docket to indicate that these results will be available on a plant-specific basis. This change was previously identified to the Staff in Reference (2-1).

Also, revised to remove pressurizer safety valve and flange from the potential missile list.

3) Design Bases for Fuel Systems Design (Chapter 4)

Reference:

(3-1) Letter LD-83-017, A. E. Scherer to D. G. Eisenhut, dated February 28, 1983 (3-2) Letter LD-83-035, A. E. Scherer to D. G. Eisenhut, dated April 26, 1983 -

(3-3) Letter LO-81-069, A. E. Scherer to D. G. Eisenhut, dated October 8, 1981 Revised Section 4.2 to incorporate the conclusions of the System 80" fuel stress, strain, strain fatigue, assembly lift-off and CEA axial growth analyses. References (3-1) and (3-2) previously transmitted to the Staff

! the results of these analyses and provided a draft of the revised sections of CESSAR-F.

Changes were also made to Section 4.2 to update and clarify the section to be consistent with an earlier response (Reference 3-3) to a NRC Question.

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Mr. C. Thomas LD Attachment Page 2

4) Reactor Coolant System and Connected Systems (Chapter 5)

Reference:

(4-1) Letter LD-82-029, A. E. Scherer to D. G. Eisenhut, dated March 4, 1982 Revised to incorporate an Interface Requirement (IR) on Emergency Feedwater System reliability. This change is consistent with C-E's discussion of the System 80" rapid depressurization and decay heat removal capability previously submitted for Staff review via Reference (4-1).

Revised to add clarification to certain IR's and provide information on NSSS heat loads previously identified as "later".

5) Engineered Safety Features (Chapter 6)

Deleted materials from the list of principle Engineering Safety Features pressure retaining materials which were in fact not used in the System 80" NSSS.

Deleted the IR on Safety Injection System component loading times. This IR was redundant to the IR for Safety Injection flow delivery and therefore unnecessa ry .

6) Iodine Removal System Licensing Report (Appendix 68)

Reference:

(6-1) Letter LD-83-034, A. E. Scherer to D. G. Eisenhut, dated April 22, 1983 Revised the IR on post-LOCA containment sump pH and access to Iodine Removal System as indicated in Reference (6-1). The changes are intended to close out Staff review of Confirmatory Item 12 of the CESSAR-F SER.

7) Instrumentation and Controls (Chapter 7)

Reference:

(7-1) Letter LD-81-069, A. E. Scherer to D. G. Eisenhut, dated October 8, 1981.

Revised instrument characteristics to reflect design changes made for compliance with Regulatory Guide 1.97 and NUREG 0588.

Revised shutdown cooling suction line isolation valve setpoints to be consistent with LTOP results previously provided in response to NRC question 440.1 (Reference 7-1).

I Mr. C. Thomas LD Attachment Page 3

8) Electric Power (Chapter 8)

Deleted the reference to Safety Injection System IR that was removed in Item 5 above,

9) Auxiliary Systems (Chapter 9)

Revised to include an item in CVCS FEMA which was inadvertently omitted in the previous amendment.

10) Initial Test Progran (Chapter 14)

Revised waterhammer test to incorporate the conclusions of the San Onofre Unit 2 feedring collapse investigation. Test revised to prevent damaging waterhammer and establish criteria for evaluation of test results.

11) Accident Analysis (Chapter 15)

Reference- (11-1) Letter LD-83-019, A. E. Scherer to D. G. Eisenhut, dated March 10, 1983 Revised Section 15.3.3.1, " Single Reactor Coolant Punp Rotor Seizure with Loss of Offsite Power", to include a stuck-open Atmospheric Dump Valve as required by the Staff. The results of this analysis were previousiy submitted to the Staff via Reference (11-1) in response to Confirmatory Item Number 16.

12) fy thods for Analysis of the Loss of Feedwater Inventory Events (Appendix 15B)

Reference:

(12-1) Letter LD-83-036, A. E. Scherer to D. G. Eisenhut, i dated April 26, 1983 l

Revised Appendix 15S to include additional information on the srall feedwater line break analysis in response to Confirmatory Item Number 15.

The revised appendix was previously P.ubmitted to the Stoff via reference (12-1).

13) Address of Additional Licensing Matters Issued Since the Regulatory Guide Cut-Off Date of CESSAR PSAR (Appendix A)

Revised statement on Regulatory Guide 1.-97, updating position.

14) Address of TMI Action Plan (Appendix B)

Revise to upgrade instrument ranges to reflect revised design information.

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UllITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the flatter of: )

)

Combustion Engine? ring, Inc. ) DOCKET N0. STN 50-470F

)

Standard Plant )

APPLICATION FOR REVIEW 0F "COMBUSTI0il EllGIflEERING STAllDARD SAFETY ANALYSIS REPORT,"

Af1ENDMENT NO. 8 J. M. West, being duly sworn, states that he is Vice President, Nuclear Power Systems, Combustion Engineering, Inc.; that he is authorized on the part of said corporation to sign and file with the Nuclear Regulatory Commission this Amendment; and that all statements made and matters set forth therein are true and correct to the best of his knowledge, information and belief.

COMBUSTION ENGINEERING, INC.

By O- nq c mwl'/

J. M: llest c N

• of]d Vice President Nuclear Power Systems Rit _/O..*_.;, _fUd 19 83 THE'dG M. Chr.ul. UARy PUguc

'Ce u Cen.,:r. c ha. 5037 Cc.nai.n u tq:rcs!/ncit 31,1933

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