ML20054C090

Forwards Amend 7 to CESSAR-F.List of Topics of Revision Encl

ML20054C090
Person / Time
Site:	05000470
Issue date:	04/16/1982
From:	Scherer A ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
To:	John Miller Office of Nuclear Reactor Regulation
Shared Package
ML20054C091	List: ML20054C090 ML20054C100
References
TASK-AS, TASK-BN-82-34 BN--82-34, BN-82-34, LD-82-045, LD-82-45, NUDOCS 8204200020
Download: ML20054C090 (4)

Text

C-E P;w:r Sy:t::ms Tel 203/688-1911 Combustion Engineenng. Inc Telex 99297 1000 Prospect Hill Road Windsor, Connecticut 06095 POWER H SYSTEMS Docket No.: STN-50-470F April 16,1982 LD-82-045

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Mr. James R. Miller, Chief g \

Standardization and Special Projects Branch NECEggg Division of Licensing -

7 U. S. Nuclear Regulatory Commission 9j aApg 2 O 1982g' 2 Washington, D. C. 20555

Subject:

CESSAR-F Amendment No. 7

<b P

Dear Mr. Miller:

Combustion Engineering, Inc. (C-E) hereby submits for your review seventy (70) copies of Amendment No. 7 (non-proprieta ry) to CESSAR-F. This amendment includes a variety of changes which are listed and explained in the attached table.

If we can be of any additional assistance, please feel free to contact either myself or Mr. G. A. Davis of my staff at (203)688-1911, Extension 2803.

Very truly yours, COMBUSTION ENGINEERING, INC.

7 N

A. E. Scherer Director Nuclear Licensing AES:ctk Attachment 1 foo9 6 3f'10 8204200020 820416 PDR ADOCK 05000470 K PDR u .

AMENDMENT NO. 7 TOPICS OF REVISION

1) Environmental Design of Mechanical and Electrical Equipment (Chapter 3)

Section 3.11 was revised to include the ramifications of Revision 3 to topical report CENPD-255 which incorporated EG&G comments on that topical. These changes were previously transmitted in reference A.

2) Clarification of Structures, Systems and Components (Chapter 3)

At the request of the Environmental Qualification Branch, Table 3.2-1 which discusses safety class, quality class and seismic category for plant components, was revised in the following areas: containment isolation valve QA requirements, quality class for reactor coolant pump auxiliary components, QA requirements for safety related Instrumentation and Controls and all Quality Class 2 components. This table was revised to include all safety class 1, 2 and 3 valves in the reactor coolant system.

3) Missile Protection (Chapter 9)

Table 3.5-1 was revised to include a Control Rod Drive Assembly Inpact dimension which is more consistent with the actual design.

4) NSSS Seismic I Active Valves (Chapter 3)

Section 3.9.3 was revised, per NRC request in SER confirmatory item 2, to provide a more definitive pump and valve operability assurance program to clari fy the qualification methodology and to provide the acceptance criteria used in the program.

5) CEDM Cooling and Miscellaneous Changes (Chapter 4)

The minimum cooling requirements for the Control Element Drive Mechanisms were revised to reflect test results. Numerous clarifications and revisions were made to Chapter 4 concerning LOCA impact loads and stresses, fuel assembly design, UOy specific heat, fuel rod internal pressure, cladding stress strain limits and CEA differentiation to close out SER open item 2 and confirmatory items 3 and 4. These changes were previously transmitted in References B, C and D.

6) Low Temperature Overpressure Protection (Chapter 5)

Changes were made to the discussions of the Shutdown Cooling System (SCS) and Low Temperature Overpressu re Protection (LT0P) concerning LTOP related alarms and SCS valve setpoints to close out Palo Verde SER confi rmatory item 10 These changes were previously transmitted in Reference E.

7) Reactor Vessel Cavity Flooding (Chapter 5)

The reactor vessel cavity flooding interface was revised to maintain consistency with engineering design requirements.

8) Containment Isolation Valve Power and HPSI Flow Meters (Chapter 6)

Chapter 6 was revised to reflect NRC requirements for emergency power for containment isolation valves and to provide individual HPSI pump ultrasonic flow meters to provide alarming on low flow. SER confirmatory item 11 was closed out by these changes which were previously transmitted in Reference E.

9) Baron Oilution Alarm System (Chapter 7)

Section 7.7.1 was updated to include a description of the Boron Dilution Alarm System (BDAS) for technical specification modes 3 through 6 for protection against boron dilution in these modes. SER confirmatory item 13 was closed out by these changes which were previously transmitted in Reference E.

10) Chemical and Volume Control System Valve Power Requirements (Chapter 9)

Chapter 9 was revised to reflect emergency power supply to CVC valves to permit the plant to be brought to cold shutdown from the control room.

SER confirmatory item 8 was closed out by these changes which were previously transmitted in Reference E.

11) Steam Generator Water Hammer Tests (Chapter 14)

Changes were made to two startup tests in Chapter 14 to include checks for waterhammer to address NUREG/CR-1606. Waterhammer is discussed in Appendix C.5 of the SER.

12) Chapter 15 Re-write Completion (Chapter 15)

The revision of Chapter 15 to be consistent with the Standard Review Plan was completed. The entire Chapter 15, including appendices, was revised in this amendment to close out SER confirmatory items 14,15,17 and

18. In addition, the fuel handling accident was changed to comply with Reg. Guide 1.25 to close out SER confirmatory item 19. These changes were previously transmitted in References F and G.

1

References:

l A. Letter A. E. Scherer to D. G. Eisenhut, LD-82-008, dated 1/29/82 B. Letter A. E. Scherer to D. G. Eisenhut, LD-82-018, dated 2/18/82 C. Letter A. E. Scherer to D. G. Eisenhut, LD-82-030, dated 3/11/82 D. Letter A. E. Scherer to D. G. Eisenhut, LD-82-003, dated 1/11/82 E. Letter A. E. Scherer to D. G. Eisenhut, LD-82-014, dated 2/11/82 F. Letter A. E. Scherer to D. G. Eisenhut, LD-82-016, dated 2/12/82 G. Letter A. E. Scherer to D. G. Eisenhut, LD-82-040, dated 3/31/82

[

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of: )

Combustion Engineering, Inc. DOCKET NO. STN-50-470F' Standard Plant APPLICATION FOR REVIEW 0F

" COMBUSTION ENGINEERING STANDARD SAFETY ANALYSIS REPORT,"

AMENDMENT NO. 7 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 b n~%t 4 J. M.< West Subscribed ar.d sytorn to before rne Vice President Nuclear Power Systems This- 'k day of 8#//19 8 Ad?u x E' M ai g , .

DWil E. SANDEit. HDTARY PUCUC Sta:: of Camacdcut NJ. 613?d Com 236ca h,cest,5,qq n Igg