ML19309A271

From kanterella
Jump to navigation Jump to search
Discusses Reactor Coolant Pressure Boundary Component Periodic Testing & Insp Assessing Structural & Leaktight Integrity.Sample Tech Specs Encl for Guidance in Revising License Amend Request to Be Submitted within 45 Days
ML19309A271
Person / Time
Site: Rancho Seco
Issue date: 09/24/1976
From: Reid R
Office of Nuclear Reactor Regulation
To: Mattimoe J
SACRAMENTO MUNICIPAL UTILITY DISTRICT
Shared Package
ML19309A267 List:
References
NUDOCS 8003270596
Download: ML19309A271 (3)


Text

s

?

-e DISTRIBUTION:

September 21, 1976 NRC PDR JRBuchanan Docket File /

L PDR ACRS (16)

Docket no. 50-312 Dross ORB #4 Rdg VStello KRGoller Sacramento Municipal Utility District ATTN: Mr. J. J. Ma ttimoe TJCarter Assistant General Manager OELD and Chief Engineer 0I&E (5) 6201 S Street RReid P. O. Box 15830 VRooney (2) j Sacramento, California 95813 RIngram DEisenhut Gentlemen:

MFairtile TBAbernathy RE: RANCHO SECO NUCLEAR GENERATING STATION General Design Criteria '(GDC) 30 and 32 of Appencix A to 10 CFR Part 50 require that components that are part of the reactor coolant pressure i

boundary recei.ve periodic inspection and testing of critical areas to assess their structural and leaktight integrity.

The. steam generator tubes ' constitute' over 507, of the ' area of the total-primary system

~

pressur.e-retai.ning boundary in. pressurized water reactors.

In your i

letter of October 9',197a, you agreed to perfom an eddy current in-spection of stean generator tubes during your first refueling outage.

~

As we informed you in our ' letter dated July 31, 1975, we intended to i

request that you propose Technical Specifications incorporating the new inspection requirenents of the soon-to-be-re*:ised Regulatory Guide 1.83.

Regulatory Guide 1.83 has now been revised; therefore, we request that you suomit proposed Technical Specifications consistent with the enclosed model technical specifications which are based on Revision-1 of R.G.1.83, dated July 1975.

Both the original and revised R.G.1.83 refer to a tube plugging linit and plugging criteria, but neither provides guidance on how these are to -

a be ' qua n ti fi ed'.-

The plugging linit in the enclosed codel technical snecifi-cations is based on the minimum-tube wall thickness needed to Nintain tube jintegrity during a LOCA combined with a safe shutdown earthonake and an operational allcwance to account for time intervals between inspections.

We have concluded that plugqing limits that are based on these considerations satisfy the requirements.of the GOC and are acceptable to us.

Stean generator tube leakage can be an indication of tube degradation; there-fore, we have. concluded that a leakage linit and a linitinq condition for operation should be included in the technical specifications to ensure tinely action in the event of steas genarator tube degradation.

A leakage limit such as the one in the enclosed c.odel technical snecifie3tions is acceptable j

l to us..

g 3o0s270 596

5 o

4 i

Sacramento Municipal Utility j

District

. 1 1

Certain types of stean generators have completed the first cycle of 00-eration with tube inspection results that have indicated little discern-ible degradation.

These early-in-life inspection results nay not ne indicative of the total 40 year design life of steam generator tunes l

in terrs of tube integrity. Therefore, we have concluded that sur-veillance of steam generator tuce integrity should be covered by technical specifications for all facilities including those where early inspection

~

cycles.have not indicated any discernible or increasing degradation.

The enclosed model technical specifications gives credit for favorable i

.early inspection results by extending subsequent inspection intervals and keeping at a mininum the nur.ber of tubes to be probed.

We request that within 45 days of receipt of this letter, you revise or resubmit your reouest for a license arendnent usino the enclosed v.odel tehical specifications for guidance.

The model technical specifications shouid 'be appropriately adapted to your specific fornat and to the number of.stean generators in your plant.

Sincerely, l

w l

n -~.

. f. % d.TCQ g,

.r 2,

s f

11

' Robert W. Reid, Chief A

f Operating Reactors Branch 84 Divis. ion of Operating Reactors

Enclosure:

t tiodel Technical Specifications cc w/ enclosure:

See next.page 6

f i

l-i l

.. ORB.#4 : D..O. R ORB. #.4:..00. R....,C-0 #4300R

/

o,,0..

  • l VRooney

_.MFairtile.:rrL 4tRe d _

-.N.

. [N

..r.

  • l Forum AEC 318 (Rev. 9-53) AICM 0240 W u. e. eov.RNM.NT PRINTING OFFIC.s g e74.sas.g es

"f

E e

..F p

- F,., -

A e

o Sacranento Municipal Utility District 1

)

cc: David S. Kaplan, Secretary and raneral Counsel 6201 S Street i

Post Office Box 15830 Sacramento,._ California 95813 i

Business and Municipal Departa nt i

- Sacramento City-County Library S28 I Street l

Sacramento, California 95814 4

f e..

N a

g.-

~

- m y-:

> ~

r..p,,..:..

as - -

1 1

i

-v

2.,w'$

w,

~

~a g

n: ;,

,", k' '

.* 't k,,

- f.

-~e, t

f 4

'.e s

8 t

i i

?

b

(-

8

. p

  • e A

F E

}=,

4

~

.c L_

e. 'j..:

L f

F s,....M.

...3.-

sm......,..

.m..

.w.w..a

..+a+---*e...--->e==e+.

euRN AME b h

~ O ATS b

- Form AFC 318 (Rev. 9 53) ABCM 0240

_ # u. s. oovannuant pasatino orrects se74.sas.see

,