ML17324A572

From kanterella
Jump to navigation Jump to search
Forwards Reactor Containment Bldg Integrated Leak Rate Test, Completed on 850830.Test Performed as Specified in Rev 0 to Surveillance Test Procedure **1 Thp 4030 STP.202, ANSI N45.4 - 1972,FSAR & Tech Spec 4.6.1.2
ML17324A572
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 01/08/1986
From: Alexich M
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To: Harold Denton
Office of Nuclear Reactor Regulation
Shared Package
ML17324A575 List:
References
AEP:NRC:0968, AEP:NRC:968, NUDOCS 8601290124
Download: ML17324A572 (4)


Text

"." '>>'

ICSIKk~RRllkil

'ECULATORY, 'ORNATION FACIL: 50-315 Donald AUTH. NAME C.

AUTHOR

.-- GaJlsXR".-:

Cook Nuclear Power AFFILIATION DISTRIBUTION .BYiN: {RLIDB>

"- ---I .

Plant. Unit ii Indiana &

- T~

05000315 ALEXICH> M. P. Indiana 5 Michigan Electric Co.

RECIP. NAME RECIPIENT AFFILIATION DENTON> H. R. Office of Nuclear Reactor Regulationi Director (post 851125

SUBJECT:

~ Forwards Reactor Containment Bldg Integrated Leak Rate Testi" completed on 850830. Test performed as specified in Rev 0 to Surveillance Test Procedure 441 THP 4030 STP. 202>

ANSI N45. 4 1972> FSAR 8< Tech Spec 4. 6. 1. 2.

C~J.

DISTRIBUTION CODE: A01/D COPIES RECEIVED: LTR i'NCL TITLE: OR'ubmittal: Append J Containment Leak Rate Testing i SIZE:

NOTES: 05000315 OL: 10/25/74 RECIPIENT COPIES REC IP IENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PNR-A PD4 PD 01 5 NIQQINQTON~ D 1 }y INTERNAL: ACRS 07 10 ADM/LFMB ELD/HDS3 08 1 NRR BNR ADTS NRR PNR-A ADTB 1 DTS NRR/DBRO DIR 1 RKQ FILE 04 RQN3 1 EXTERNAL: 24X 1 1e LPDR 03 NRC PDR 02 NSIC 05

~ )( -,I,4 ( i+a aAy pyu e~ (8+O~E>)

r=~Za ( RBSa) pals (c, pss

~>> C<C~+< Y)A~

itj TOTAL NUNBER OF COPIEB REQUIRED: LTTR hg ENCL

>" )<<);~'jl'L ",")

'Ol )FP, Ht <<'f't .Gati l)>~'I"~'t<<S <<s + j4 t: i1 "jlhfkiO;<<<<i <)"'

Clff ~ << <<

v r<<+

bV 0 ~

r

. 0 + .'i.lLX j <'<<(>>.' "Sr<<rr Sl S\

TbKF,',j ) ~ <<

lt Crier)L 4 <<g

..jl. a s

<<sr/<<g<<s<<Tgk,)jT ')I <<r<<jg)Ij, * )SP.

L ll ~~.< ji .r jl '<<l>> )l"l3l)')'; " VQ> <<'r CU.<<fj.<<~ 6'.~,.C.L 'k" <<<<

r <<" r'

'<<) A ','0 I; tO<<'<< ~,.',,) 0" <<

W l')

Q SS')<<( l<<Prf>'~, r< i.'j5lr . f ..<<~r

)') f.':<<Q ' f (<<S QP<<j s .. 'Dg ) II ~,

erg P r~ s t) l, I'I<<<<<<IS

,. 'IC' I,j

'S )

waW:M 44r " XSk4lLla. 4SJaP INDIANA 8 MICHIGAN ELECTRIC COMPANY P.O. BOX 16631 COLUMBUS, OHIO 43216 January 8, 1986 AEP:NRC:0968 Donald C. Cook Nuclear Plant Unit No. 1 Docket No. 50-315 License No. DPR-58 INTEGRATED LEAK RATE TEST Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Denton:

Pursuant to the provisions of 10 CFR 50, Appendix J, Section V.B, enclosed is a copy of the Reactor Containment Building Integrated Leak Rate Test (ILRT) for D. C. Cook Unit 1 which was successfully completed on August 30, 1985. The ILRT was performed as specified in surveillance test procedure **1 THP 4030 STP.202, Rev. 0, in accordance with the recyxirements of American National Standard ANSI N45.4 1972, the Code of Federal Regulations, the plant FSAR, and Technical Specification 4.6.1.2.

This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to insure its accuracy and completeness prior to signature by the undersigned.

Very trul yours, L M. P. Alexich Vice President) 5[

cc: John E. Dolan W. G. Smith, Jr. - Bridgman R. C. Callen G. Bruchmann G. Charnoff NRC Resident Inspector Bridgman Oigq0124 860108 0 5000315 '

ADOCV pDR - (Itr only)

PDR , AD J. KNIONT EB (BALLARD) i )

)

EICSB (ROSA)

FSB (OANNILL)

RSB (BERLINGER) t FOB (BENAROYA)

~ ~

j. 4

> +t sca~gr ~ ~ te 4+< smack

~ $ ~

y'k

~ 0 II l

I J

'1 a II 0 I l ~

I u, II mz fl