ML20066E405

From kanterella
Jump to navigation Jump to search
Forwards Completed Questionnaire Re Steam Generator Tube Integrity,Generic Ltr 82-22.Second & Last Questions Applicable Since Initial Criticality Achieved on 821022
ML20066E405
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 11/10/1982
From: Dixon O
SOUTH CAROLINA ELECTRIC & GAS CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
GL-82-22, NUDOCS 8211150156
Download: ML20066E405 (2)


Text

,

P

^s f

SOUTH CAROLINA ELECTRIC & GAS COMPANY POST OFFICE 764 COLUMe A. SOUTH CAROLINA 29218 O. W. DixoN. JR.

YsCE PRES @ENT November 10, 1982 NUCLEAR Ol'ERATIONS Mr. Harold R.

Denton, Director Office of Nuclear Reactor Regulation U.S.

Nuclear Regulatory Commission Washington, D.C.

20555

Subject:

Virgil C.

Summer Nuclear Station Docket No. 50/395 Operating License No. NPF-12 Generic Letter 82-22

Dear Mr. Denton:

The response to the questionnaire concerning steam generator tube integrity, Generic Letter No. 82-22, is attached.

Only the second and last questions are applicable to the Virgil C.

Summer Nuclear Station due to the fact that initial criticality was achieved on October 22, 1982.

Yours very truly, s

O. W.

Dixo, Jr.

WRM:OWD/fjc

Attachment:

cc:

V.

C.

Summer G.

H.

Fischer H. N. Cyrus T.

C.

Nichols, Jr.

O. W.

Dixon, Jr.

M.

B. Whitaker, Jr.

J.

P. O'Reilly H.

T.

Babb D. A.

Nauman C.

L.

Ligon (NSRC)

W. A.

Williams, Jr.

R.

B.

Clary O.

S.

Bradham A. R.

Koon g

Q\\

M.

N.

Browne G.

J.

Braddick J.

L.

Skolds J.

B.

Knotts, Jr.

B. h.

Bursey NPCF File 8211150156 821110 PDR ADOCK 05000395 P

PDR L

..g

)

U. S. NUCLEAR REGULATORY COMMISSION Approved by OMB 3150.0092 STEAM GENERATOR-RELATED - QUESTIONNAIRE RESPONSE BY YEAR 1979 1980 1981 1982 HOW MANY DAYS OF UNSCHEDULES OUTAGES CAN BE ATTRIBUTED T0 g[

g STEAM GENERATOR-RELATED DIFFICULTIES PER YEAR AT YOUR SITE?

DURlNG EACH OF THE YEARS IN QUESTION, HOW MANY STEAM GENERATOR TUBES HAVE BEEN PLUGGED IN EACH STEAM GENERATORf

  1. //l SLEEVED IN EACH STEAM GENERATOR?

WHAT HAVE BEEN THE TOTAL COSTS AND SPECIFICALLY REPLACEMENT POWER COSTS ASSOCIATED WITH STEAM GENERATOR MAINTENANCE, REPAIR AND REPLACEMENT AT YOUR PLANT?

WHAT riAS BEEN THE TOTAL OCCUPATIONAL RADIATION EXPOSURE (IN PERSON-REMS) CAUSED BY STEAM GENERATOR MAINTENAhCE?

REPAIR / REPLACEMENT?

WHAT PERCENTAGE OF TOTAL ANNUAL EMPLOYEE DOSE HAS BEEN ATTRIBUTABLE TO STEAM GENERATOR RELATED WORK AT YOUR SITE (S)?

mig THE YEARS IN QUESTION HOW MANY WORKERS HAVE RECEIVED MEASUREABLE RADIATION 005ES:

FOR STEAM GEt{ERATOR RELATED WORK?

kHAT PERCENTAGE OF THE TOTAL WORKFORCE. DO THESE WORKERS REPRESENT?

HOW MANY TEMPORARY WORKERS (defined by the NRC as all workers other than those hired directly by nuclear power plants on a conventional, long-term basis) RECEIVED DOSES FROM STEAM GENERATOR-RELATED WORK AT YOUR FACILITY EACH YEAR?

WHAT PERCENTAGE OF TOTAL WORKERS INVOLVED WITH STEAM GENERATOR-RELATED WORK 00 TEMPORARY WORKERS, REPRESENT?

THE TOTAL WORKFORCE DO TEMPORARY WORKERS REPRESENT?

HAS YOUR COMPANY USED INDEPENDENT FIRMS TO FIND TEMPORARY EMPLOYEES WHO HAVE RECEIVED AN OCCUPATIONAL DOSE FROM STEAM

, GEJEP.ATOR-RELATED WORK?

y V

v v

0010U ANTICIPATE MAJOR STEAM GENERATOR REPAIRS IN ANY OF YOUR UNITS IN THE NEXT FIVE YEARS, AND IF SO HOW MUCH WOULD THESE REPAIRS COST, PLEASE SPECIFY.

In 1983, we expect a major outage to modify our model D-3 Westinghouse preheat steam generators.

This work will be performed under warranty.

SCE&G plugged five tubes as a result of pre-initial criticality multi-frequency eddy current inspection.