ML20042G978

From kanterella
Jump to navigation Jump to search

Forwards Safety Evaluation Accepting Util 890929 Request for Relief from Hydrostatic Pressure Test Requirements for RCS, Per Section XI of ASME Boiler & Pressure Vessel Code. Recommends That Test Be Performed Near Lowest Temp for RCS
ML20042G978
Person / Time
Site: Sequoyah  
Issue date: 05/11/1990
From: Black S
Office of Nuclear Reactor Regulation
To: Kingsley O
TENNESSEE VALLEY AUTHORITY
Shared Package
ML20042G979 List:
References
TAC-75030, TAC-75031, NUDOCS 9005160364
Download: ML20042G978 (3)


Text

'~'

~-

/(

/pn ago UNITED ST ATES M

NUCLEAR AEGULATORY COMMISSION b3' E\\, f.,

g W ASHINGTON, D. C. 20555 g

s 8

o

),.

May 11, 1990 l

j=

Docket Nos. 50-327 and 50-328 Mr. Oliver D. Kingsley, Jr.

j..

Senior Vice President, Nuclear Power Tennessee Valley Authority 1-6N 38A Lookout Place c

1101 Market Street Chattanooga, Tennessee 37402-2801 h 4r Mr. Kingsley:

SUBJECT:

RELIFF FROM CODE HYDROSTATIC PRESSURE TES1 REQUIREMENTS FOR REACTOR I

COOL!sNT SYSTEM (TAC 75030/75031) - SEQUOYAH NUCLEAR PLANT, UNITS 1 i'

AND 2

_A Dy letter dateo September 29, 1989, you requested relief f rom che hydrostatic t.

5 pressure test requirements of Section XI of the American Society of Mechanical

.s Engineers Boiler and Pressure Vessel Code,1980 Edition through the Winter

' ;[

1981 Addenda (Code).

The relief was for the reactor coolant system (RCS) for i

t.oth units.

The relief is associated with the plant modifications during the 1990 Cycle 4 refueling outage for each unit to remove the u[per head injection

=

system and the RCS resistance temperature dc'. ice (RTD) nianifolds.

=

i- -

You proposed, as an alternative method to the Code test, to perform a system leakaoe test of the RCS in Mode 3 with the system at operating pressure and temperature, and a Code NDE examination of the welds. As discussed in the enclosed Safety Evoluation (SE), the staff has evaluated your request for relief from the Code requirements and concludes that the alternative method of testing proposed by you provides an acceptoble level of quality and safety at Sequoy ah.

Granting relief from Code requirements is authorized by law, pursuant to 10 CFR 2

50.55a(a)(3), where the proposed alternative to the Code requirements would 4

provide an acceptable level of quality and safety at the plant.

Therefore, I2 based on the enclosed SE and pursuant to 10 CFR 50.55a(a)(3) of the Coninission's regulations, the Tennessee Valley Authority is granted the requested relief from the Code for Sequoyah for the moaifications to remove the UHI system and RTD manifolds, as documented in the enclosed SE.

As you explained, o Code hydrostotic pressure test of the RCS will be performed near the end of the 10-year 3

3 R

?

kIO!

a 9005160364 900511

{l DR ADOCK O$00 J,7 i

a>

s m

a

.\\

Mr. Oliver D. Kingsley, Jr.

2-

-May 11, 1990' finst.rvice ' inspection interval for Sequoyah as part of the Sequoyah inservice

' inspection program. The staff recommends that this test be performed near the lowest temperature for the RCS consistent with fracture prevention criteria, Sincerely, t

2 4 anne. luck,gssistant DJ

a. h.

Suz for Projects TVA Projects-Division Office of Nuclear Reactor Regulation.

Enclosure:

Safety Evaluation q

cc w/ enclosures:

See next page L

Distributice

-Docket File NRC PDR I

-Local POR L

SQN Reading L

ADSP Reading

~

?

D. ' Crutchfield

-T Quay.

B. D.'Liaw S. Black H

R. Pierson-L B. Wilson L.-Watson' JJ.- Brady

-LA J.'Donohew

.000 l p-lB. Grimes J'

.E.' Jordan L'.'

'ACRS-(10) a 11

.GPA/CA LP T F. Hebdon u

l>

l t:0GC W;

.p..:............:...........:.........:............:.......-....

.l l:l. 0FC, ;:N :T

)M :TVA1 A g,.....:.

r... :...,

as
SB k
/, Deut.

'JNAMEj:

........: (....M....

..:.f......=y

....:K/D/90'

/ /90

s / T/90 '

CH;DATE:

.w.

r m

a.

L

'0FFICIAL RECORD: COPY q

l-O. m 1

N..

'W

  • .7. ' fli.

.~

y.. a uf.

. 1 7;

Mr.' Oliver D. Kingsley, Jr. :1 ff cC;

~

'Mr. Marvin Runyon, Chairman Mr. Joseph Bynum, Acting Site Director-Tennessee Valley Authority Sequoyah Nuclear P hat.

ET 12A 7A; Tennessee Valley..athority-400 West' Summit Hill Drive P. O. Box 2000 Knoxville, Tennessee 37902 Soddy Daisy, Tennessee : 9379 Ar. C. H. Dean, ir., Director Mr. Mark J.-Burzynski i

Tennessee Vallsy Authority Site Licensing Manager i

ET 12A-11A Sequoyah Nuclear Plant 1

400 West'Sumit Hill Drive P. O. Box 2000 Knoxville, Tennessee. 37902 Soddy. Daisy, Terassee 37379 Mr.l John B. Waters, Director County Judge Tennessee Valley Authority Hamilton County Courthouse 4

ET 12A 9A' Chattanooga, Tennessee.37402 400 West Summit Hill Drive.

Knoxville, Tennessee -37902 Regional Administrator, Region II U.S. Nuclear' Regu'latory Comission Mr. W. F. Willis 101 Marietta Street,-N.W.-

Chief Operating'Of ficer Atlanta, Georgia-30323 ET 128 16B 400 West Summit Hill-Drive Mr. Kenneth M. Jenison Knoxville, Tennessee 37902 Senior Resident Inspector Sequoyah Nuclear'Plarit.

General Counsel U.S. Nuclear Regulatory Commission 1

Tennessee Valley Authority 2600 Igou Ferry Paad E

400 West Summit Hill-Drive Soddy Daisy, Tennessee 37379

~

ET 116 33H-h Knoxville, Tennessee 37902 Mr. Michael H. Mobley, Director Division of Radiological Health Mr. Dwight Nunn T.E.R.R.A. Building, 6th Floor.

l Vice President, Nuclear Engineering 150 9th Avenue North r

j

-Tennessee Valley Authority N4shville, Tennessee -37219-5404 t

'6N-38A Lookout Place q

L b

1101.. Market Street Dr. Henry Myers, Science Advisor H

Chattanooga, Tennessee 37402-2801 Comittee 'on Interior and Insular Affairs Dr. Mark 0. Medford U.S. House of Representatives b

Vice President and Nuclear Washington, D.C.

20515 Technical Director I

Tennessee Valley Authority Tennessee Valley Authority 6N 38A Lookout Place Rockville Office l

E Chattanooga, Tennessee 37402-2801 11921 Rockville Pike Suite 402 Mr. Edward G. Wallace Rockville, Mary!und 20852 l'

-Manager, Nuclear Licensing

);

and Regulatory Affairs

+

Tennessee Valley Authority SN 157B Lookout Place Chattanooga, Tennessee -37402-2801

~

f

\\,,

t t

e

-.