ML19093B017

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Attached Herewith Are 40 Copies of Additional Information Concerning the Steam Generator Replacement at the Surry Power Station
ML19093B017
Person / Time
Site: Surry  Dominion icon.png
Issue date: 04/27/1978
From: Stallings C
Virginia Electric & Power Co (VEPCO)
To: Case E, Schwencer A
Office of Nuclear Reactor Regulation
References
Download: ML19093B017 (6)


Text

VIRGINIA ELECTRIC AND PowER COMPANY RICHMOND,VIRGINIA 23261 April 27,

  • 1978-
  • Hr. Edson G. Case, Acting Director Serial No. 222 Office of Nuclear Reactor Regulation PO&M/JTB:das U.S. Nuclear Regulatory Commission Docket Nos. 50-280 Washington, D. C. 20555 50-281 License Nos. DPR-32 Attention: Mr. A. Schwencer, Chief DPR-37 Operating Reactors Branch 1

Dear Mr. Case:

Attached herewith are 40 copies of additional infonnation concerning the steam generator replacement at the Surry Power Station. This information is being submitted as Revision No. 2 to the document "Steam Generator Project, Surry Power Station, Unit Nos. 1 and 211 submitted in our letter dated August 17, 1977, Serial No. 351. The revision contains responses to questions posed by the Staff in your letters of December 27, 1977;- January 20, 1978; February 1, 1978 and February 2, 1978.

The questions and responses are contained in Section 9. For reference purposes, the questions contain an alphanumeric designation. The alpha desig-nation refers to the NRC letter date, i.e. A is for 2/2/78,; B is for 2/1/78, C is for 1/20/78 and Dis for 12/27/77. The numeric designation is the same as the NRC numbering system in a specific letter.

The document should be revised in accordance with the attached instruc-tions. The remaining responses will be submitted in the near future.

If you have any would be pleased to meet with your staff ll(G!Jf.AltJ,1,;

da rD!lttr~

q~l-, ,9.f[CPD. -.

cc: Hr. James P. O'Reilly, Direc~r Office of Inspection and Enforcement 11001 / s I/ 'I-()

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COMMONWEALTH OF VIRGINIA )

) s. s.

CITY OF RICHMOND )

Before me, a Notary Public, in and for the City and Common-wealth aforsaid, today personally appeared Sam*c. Brown, Jr., who being duly sworn, made oath and said {1) that he is Vice President-Power

  • Station Engineering and Construction, of the Virginia Electric and Power Company; {2) that he is duly authorized to execute and file the fore-1
  • going Amendment in behalf of that Company, and {3) that the statements in the Amendment are true to the best of his knowledge and belief.

k~ _\ Giv\?n under my hand and notarial seal this ~day of

__,_~~-.....__\~--' ~-

  • My Comm i s s ion exp I r e s ~....-\ ~ I~~& ,

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~~-~ . Notary_P~

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{SEAL)

STEAM GENERATOR REPAIR PROGRAM FOR THE SURRY POWER. STATION UNIT.NOS. 1 AND 2 REVISION 2 Remove Insert Table Of Contents / Pages TC-1 thru TC-3 ~ -

Pages 6.0-1 thru 6.5-1 / ~

Pages T6-l-l thru T6-l-4v-Pages 9.A.1-1 thru 9.D.9-3

~----

1\0 General

~l Purpose 1.0-1 1.£,'\.Reason For Action 1.0-1

1. 3 S'cope Of Work 1.2-1

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1. 4 Sched.,~e 1.2-1
1. 5 Impleme'ri,ta tion Of Repair Program 1.4-1 1.6 Project O~ization 1.4-1 1.7 Quality Assur~~Program 1.6-1 1.8 Steam Generator Components 1. 7-1 2.0 "'"., \

Description Of Modified Steam Generators

2. 1 General Description '\ 2.0-1

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2.2 All-Volatile Treatment Chemist~y 2.1-1 2.3 Scope Of Modified Design

',.\, 2.2-5

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2.4 Design Improvements To Prevent And Inhibit Corrosion _ \\ 2.3-2 2.5 Design Refinements To Improve Performanc~ 2.4-3

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2.6 Design Changes To Improve Maintenance And Reliability 2.5-1 2.7 Design Bases \ \ . 2.6-1

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2.8 Engineering Details '\ 2.8-1

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2.9 ASME Code ~ 2.9-1 3.0 Removal And Installation Of Steam Generators \\.,

3.1 General 3. 0..:1 3.2 Guidelines And Criteria 3.0-1 \

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3.3-1 \

3.3 Preshutdown Activities

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  • 3.4 3.5 Postshutdown Activities Removal Activities 3.3-1 3.4-1

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e e Page No.

3.6 Installation Activities 3.5-3 3.7 Post Installation Activities 3.6-1 3.8 Startup Activities 3.6-1 4.0 Safety Considerations 4.1 Introduction 4.0-1 4.2 Comparison Of Modified Steam Generators With Exiting Design 4.0-1 4.3 Accident Analyses 4.3-1 4.4 Safety Implicating Associated With Repair Activities 4.4-1 5.-0 Environmental Activities 5.0-1

...; : 'I"-,

e ABSTRACT This document describes the steam generator repair program which will be conducted at the Surry Power Station, Unit Nos. 1 and 2, during the periods of about May - October 1978 for Unit No. 1 and February - July 1979 for Unit No. 2.

The purpose of the program is to repair the degradation which. has been caused by "denting" and associated affects and to restore the integrity of the genera-tors to a level equivalent to new equipment. The repair program will incorpo-rate a large number of design iniprovments which reflect the "state-of-the-art" technology which currently exists for steam generator design.

The repair program basically consists of the replacement of the existing steam generator lower assembly with a new one, with the upper assembly being refurbished; including new primary moisture separation equipment, and being re-used. The repair program is scheduled to commence at the beginning of a normal refueling outage, with the reactors being completely defueled while the repairs are being made. The repair effort will require that reactor coolant piping, feed-water piping and steam piping be cut, as well as the steam generator itself, to facilitate removal and installation. Access to the containment will be through the currently installed equipment hatch; therefore, concrete parts of the con-tainment pressure boundary will not be disturbed.

The safety implications and other potential effects of the repair program, both during the actual repair work and following the return of the unit to power, have been considered. It has been concluded that the repair program can be com-pleted without any adverse affects on the health and safety of the general public or the personnel engaged in the repair work. *

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