ML20148F147

Forwards Request for Addl Info Re Util Inservice Insp Program & Water Chemistry Control.Info Requested within 30 Days

ML20148F147
Person / Time
Site:	Yankee Rowe
Issue date:	12/11/1975
From:	Purple R Office of Nuclear Reactor Regulation
To:	Groce R YANKEE ATOMIC ELECTRIC CO.
References
NUDOCS 8011030849
Download: ML20148F147 (3)

Text

- - - - . . .- - .

1 l

4 DISTRIBUTION DIO 1 1 1975 Docket File SVarga ORB #1 Reading DEisenhut i NRC PDR I Docket No. 50-29 Local PDR l KRGoller j TJCarter RAPurple Yankee Atomic Electric Company ABurger  !

J A'ITN: Mr. Robert H. Groce SMSheppard Licensing Engineer OISE (3) 20 Turnpike Road ACRS (16)

Westboro, Massachusetts 01581 TBAbernathy JRBuchanan l OELD l Gentlemen: l During the recent Core XI-XII refueling outage at Yankee-Rowe, yeu performed oddy current testing of tubes in steam generators Nos.1 and

4. Your letter dated November 21, 1975 (from Mr. H. B. Autio, i Superintendent, to Mr. J. P. O'Reilly, Director, Region I Office of Inspection and Enforcement), transmitted a Licensee Event Report relating -

to Reportable Occurrence 50-29/75-10 and the eddy current testing results. You reported that indications were found on tubes in both ,

steam generators (Unitsi and 4) in excess of the acceptance limits in

) Regulatory Guide 1.83, dated June 1974. As provided for in Section 7.d.

of the Guide, we have reviewed the eddy current test results based on the particular features of the Yankee-Rowe steam generators, vis.  ;

stainless steel tubes, the thicker tube wall, and the use of all volatile chemistry. Prou this review, we have concluded that the steam l generator tubes are in an acceptable condition for continued safe I operation of Yankee-Rowe with Core XII.  ;

To further evaluate your inservice inspection program and water chemistry  :

control of the Yankee-Rowe steam generators, we request that you provide j to us within 30 days from the date of this letter the information j identified in the attachment to this letter.  ;

i Sincerely, j Original signed by'-  !

.- Tills DOCUMEtlT C0tlTAlt4S Robers A % IU}  !

g  :

POOR QUAUTY PAGES Robert A. Purple, Chief /jfj/p '

Operating Reactors Branch #1 < l Division of Reactor Licensing

Enclosure:

bec: JP0'Reilly, OISE, Region I Request for Additional Information KVSeyfrit, OISE, Headquarters, w/ enc:

ec w 802 i

. ^ see n/ ext enclosure:

page 1 0 3 0 h % C} f l oma , .._RL: 0RB# 1 ,,,, ,,,,,R,L.qRBfT) , _ , _ , , , _ , , , , , _ , , , , , _ , , , , , , , , , , _ , _ ,

A. Bur.ger: 1b,;

t. W.  ! W'

,RAf, urp 1e ,)

sum = > , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , ,

IDATE > .1. .!.N.!. .. . . . l. !. N ! ... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

Form AEC-318 (Rev. 9-33) AECM 0240 ano .4a-to-ams-i 44 Hrs ]

.i. _

'Ycnksa Atomic Elset.ric Company DEC 11 cc: Mr. Donald G.' Allen, President Yankee Atomic Electric Company 20 Turnpike Road Westboro, Massachusetts 01581 Greenfield Public Library 402 Main Street

~ Greenfield, Massachusetts 01581 s

1

== , . = . ** .e.---w. 4 w .. . .. - . , #.. .., ..w. .

- . . . . . .., m.

_ __ .. . ,, w "

w#T T Y'

l l

i REQUEST FOR ADDITIONAL INFOR.\!ATION

( YANKEE NUCLEAR POWER STATION (YANKEE-ROWE)

DOCKET NO. 50-29

\

t

1. Provide the results of all steam generator tube inspections prior to conversion from a phosphate treatment to all volatile treatment (AVT), and the results of all stea.m generator tube inspections during AVT operation. This should include:

a. Approximate date of inspection and reason for insepction

b. Number of tubes' inspected in each steam generator and identifi-cation of each tube inspected by row and column.

c. List of all tubes with eddy current indications by percent loss  ;

of wall thickness. I

d. Identifiention of all tubes plugged and the tube plugging

• limit used.

2. Describe the secondary water chemistry for six months, prior to termination of phosphate treatment and from the onset of transition to AVT to the present. This should include:

I

a. Normal specifications for steady state limits (including range of Na/PO4 ratio for phosphate treatment.

b. Transient limits.

c. Description of procedures implemented for transition from phosphate to AVT (indicating any sludge lancing performed and quantity of material removed).

d. A graph or plot of the secondary water chemistry showing the following as a function of. time for each steam generator:

(1) Phosphate concentration; (2) Sodium concentration; (3) pH; (4) Conductivity in umho/cm, applicable only for AVT; (5) liydroxide concentration, applicable only for AVT; (6) Weight of phosphate removed, applicable only for AVT.

.