ML19326C606

From kanterella
Jump to navigation Jump to search
Forwards Revision to Proposed Tech Specs Changes Incorporating B&W Proposed Rod Bow Model Into Parameter Mods for Cycle 2 Operation.Proposed Change Allowing Testing of Primary nozzle-to-vessel Welds Prior to 3.5 Yrs Encl
ML19326C606
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 01/13/1977
From: Phillips J
ARKANSAS POWER & LIGHT CO.
To: Ziemann D
Office of Nuclear Reactor Regulation
Shared Package
ML19326C607 List:
References
1-017-3, 1-17-3, NUDOCS 8004230708
Download: ML19326C606 (3)


Text

-

1 NTPy/ jy U.s. NUCLE A A f,EGULAToGY 9 mission DOCKET NUMBE A

2. m.

50-313 NRC DISTRIBUTION rom PART 50 DOCKET MATERIAL TO:

FROM:

DATE oF DOCUMENT Arkansas Power & Light Company 1/13/77 Mr. Dennis L. Ziemann Little Rock, Arkansas oATE RECEivEo J. D. Phillips 1/17/77 E ETTER KNoToRizEo PRor

  1. NPUTFoRM NUMBEFs oF CoPtES RECEIVED MRiolNAL hNCLASSIFIE D One signed CCorv DESCRIPTION ENCLoSU RE Ltr. no torized 1/13/77.... trans the Amdt. to o / change to tech specs....incorpor-following:

ating the B&W proposed Rod -Bow Model into thost parameter modifications required for Cycle 2 operation and proposed change to allow examination of the primacy nozzle to vessel THIS DOCUMENT CONTAINS yela, prior to 3 tf7 years operation rather P00R QUAUTY PAGES than after 3 1/2 years operation...

PLANT NAME:

ACKNO T TDGED Arkansas Unit No. 1

- c,

.m--

(2-P)

(21-P)

SAFETY FOR ACTION /INFORMATION FMvTun 1/17/77 RJL ASSIGNED AD:

ARCTONFD Ane MEAHCH CHIEF?

Ziemann

[d,)

MRANcW PMTTP.

JEQ1ECT MANAGER; Converse PROJECT MANAGER:

1 JJ9. ' ASST.

.Diggs -

LIC. ASST. :

N INTERNAL DISTRIBUTION MEEG FILE j SYSTEMS SAFETY PLANT SYSTEMS SITE SAFETY &

M NRC PDR,.

HEINEMAN TEDESCO ENVTRO ANALYSTS M I&E (3-)

SCHROEDER BENAROYA DENTON & MUT.T FR-MOELD

~

T.ATNAS MGOSSICK & STAFF

. ENGINEERING IPPOLITO ENVIRO TECH.

MIPC MACARRY KIRKWOOD ERNST CASE KNICHT BALLARD HANAUER SIHWEIL OPERATING REACTORS SPANGLER l

HARLESS PAWLICKI STELLO SITE TECH.

PROJECT MANAGEMENT

-REACTOR SAFETY OPERATING TECH.

CAMMILL BOYD ROSS X

EISENHUT /J:lr:3,. )

STEPP P. COLLINS NOVAK

)(

SHAO HULMAN HOUSTON ROSZTOCZY

>(

BAER PETERSON CHECK

.X BIRLER SITE ANALYSIS HELTEMES AT & I

'k CRIMES VOLLMER MELTZ BUNCH SKOVHOLT SALTZMAN X J. COLLINS RUTBERG KREGER l

EXTERNAL DISTRIBUTION CONTR OL NUMBER XJ.PDR Rn < < p l 1 v411 e. Art NAT. LAB:

BROOKHAVEN MAT T.AR _

ETIC:

REG V.IE ULRIKSON (ORNL)

M/

(*

h,NISIC:

TA PDR ASLB:

CONSULTANTS:

/ /

/

i Rr 0423070['

hACRS /4 CYS Met:9fM6/ SEFT : &. 8 [/ //wh )

~'

l NRCPoRM 195(2 76)

e Y

M GLPIN G B UILO ARKANSA9 ARK ANS AS POWER & LIGHT COMPANY A 0 sox 351 LIT TL E AOCK. A A K ANS AS 72 2 0 3. t50113 71 -4000 January 13, 1977

'M.J 9 9 f. /7

+

. 9 Wg 's A

1-017-3 h

Up $ '"77 3

p#

Director of Nuclear Reactor Regulation ATTN: Str. Dennis L. Ziemann, Chief v.5-Operating Reactors Branch #2 e

/p U. S. Nuclear Regulatory Commission A

Washington, D. C.

20555 u

g

Subject:

Ark.ansas Nuclear One-Unit 1 Proposed Technical Specification (File:

1511.1)

Gentlemen:

For your review and approval please find enclosed a revision to the proposed changes to the Arkansas Nuclear One-Unit 1 Technical Specifications for Cycle 2 operation. This revision incorporates the Babcock and Wilcox proposed Rod Bow Model into those parameter modifications required for Cycle 2 opera-tion. The affected pages of the Babcock and Nilcox prepared Arkansas Nuclear One-Unit 1, Cycle 2 Reload Report are provided as supplementary information.

The enclosed pages supercede those transmitted in our letter of December 1,1976.

At this time the Unit I refueling outage is scheduled to begin January 27, 1977, and continue for approximately 7-8 weeks.

Therefore, we are requesting that this revision be incorporated into the proposal of December 1,1976, and the revised proposal be approved and returned no later than March 1 to allow time for implementation prior to Cycle 2 startup.

Also find enclosed a proposed change to the Unit 1 Technical Specifications which would allow examination of the primary nozzle to vessel welds prior to 3 1/2 years operation rather than after 3 1/2 years operation. This change would be consistedt with the 1972 Summer Addenda of the ASME Boiler and Pres-sure Vessel CodeYJSection XI,1971.

2 2

Very truly yours, q

  • A /. 'i _

r

/

f_

^

i g

J. D. Phillips 07 Senior Vice President kN, d

c' JDP:dw N g,.,

~y

~

Attachment h'

/

327

. l' 6,

s c

W:

f T A x P AYING, INVESTO A OWNE D 0,

ME M B E R MIODLE E.OUTH UTILITIES S Y STEM

STATE OF ARKANSAS

)

)

SS COUNTY OF PUL\\ SKI

)

J. D. Phillips, being duly sworn, states that he is a Senior Vice President of Arkansas Power 6 Light Company; that he is authori:cd on the part of said Company to sign and file with the Nuclear Regulatory Comission this Supplementary Information; that he has reviewed or caused to have reviewed all of the statements contained in such Information, and that all such statements made and matters set forth therein are true and correct to the best of his knowledge, information and belief.

. - /_ h'.Y.-

d 7

/

J. D. Phi riips SUBSCRIBED AND SWORN TD before me, a Notary Public in and for the b

County-and State above named, this /3 day of

...nw

, 1976.

I

-k 0,

Notary Public My Commission Expires:

March 1, la78

.