ML20069A996

From kanterella
Jump to navigation Jump to search
Proposed TS SRs Section 4.6.G, Primary Sys Boundary Structural Integrity, Deleting SR Which Refers to ISI Program Interval,Allowing DAEC Current ISI Program Interval to Be Extended Per Ruling in Fr 57FR34666
ML20069A996
Person / Time
Site: Duane Arnold NextEra Energy icon.png
Issue date: 05/06/1994
From:
IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To:
Shared Package
ML20069A981 List:
References
FRN-57FR34666 NUDOCS 9405270029
Download: ML20069A996 (6)
v • d • e


Text

-

DAEC-1 j

'IMITING C0ttDI?!ONS FOR OPEPA?!ON SITRVEIT ? MICT FICUIPIMENTS j

G.

St ru ctu ra l Intecrity G.

Structural Intecrity The structural integrity of the 1.

In-service inspection of ASME Code i

pressure boundaries shall be Class I, class II and Class III j

maintained at the level required components shall be perforsned in by the original acceptance accordance with Section II of the standard throughout the life of ASME Boiler and Pressure Vessei i

the plant.

Code and applicable m aada as required by 10CFR50, section i

50.55a(g), except where specific written relief has been granted by the NRC pursuant to 10CFR50, section 50.55a(g)(6)(1).

  • :T: ' iS ;--- 12 r;;1 f::

=

"..,, '. r s. n it:. '. r;; 11 -

7_ q. n

.,,i 2.

In-service testing of AsME Code Class I, Class II and class III i

pumps and valves shall be performed in accordance with section II of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10CFR50, section 50.55a(g), except where specific written relief has been granted by the NRC pursuant to 10CFR50, section 50.55a(g)(6)(1).

a.

The second 10-year interval for the inservice testing program demeribed above ccausenced on February 1, 1985.

Amendment No. 52, 169, 183 3.6-8 9405270029 940506 PDR ADOCK 05000331 kT3

,D P

PDR

.1 I

8 1

DAEC 1 4

.-. 4.-..

-.-i.

.ww

n. u -

r:_

. in...

...1

u. -

6 v j w.,.

, u, b i

Jwi * 'w6 y

v.

ww i

i..

-w v

y.r w

a.

i

.. -,.. i.,

i P RJ_f % 4 I. a u.

_s n. A O s e e.,, e.-

4 ! A e. e..a l.#.% A ^

  • A. e t. E. A.n f I.
e. e. own.. nxa d.

n_n E A. L....

e m a g h e.,

.k a m..s. i r, a n #.

.s S,

-. -,., ',, v 107C Ph4e 4nta,i,s.1

.s. e., n. c. a. n,, n A.. ( ^ e.

O 3w sr v,

.r.

s

---.,Ib

..z%'43,WJ 1.

,n,n

,n

.- _,.,~... = -:

..:--. --J J J b b*

o 64 A4# W~I.7 I

' 'bb J.

ia.i4 VI

'bb

.I V IJ, 6s b 3V'I

..y....d v-

..b e

J 4.' ' J L u '-. _ _ _:_.-_..qLWEG

-- sm

,mer in

. m..

,,-.,e

'bE' V

VbbVuG3 se, Aswd*

-g n._

____1. in,,..,.._ 4. m e+-4

4..e.
2. _--

2...,--.4.-.-

u..-.. m.

.o.

i n.,......

-h-n,.O.,

4..

.-,_a.,,.2,_2 m,2

2. n. n. e.. n..

..a n-.-m--

1. c

.m..-

--.1.,em,3t, ^'. ' hm-

', "..., ',su--'..-.

n" ',

~

22----

4,,,,,,,,4,....

.w n,,

w.

..,..,,, t 14. =. 6..- 18.01,

.,., k. ~4 m + _.,.,

6. h.-
1. f 4 6.* h 4. -.,.,

4AA

i. n. O n. c.A. i. e. 4. o, 2 6. w. ~,.am...A.=..6..

_s e. A_.n A. 4. f 4..,

4. a....,,.,

,6, 6

..J P. f. M,

f. n. E f.*.

in

. ~

evin%

ASME Sec.% $

Visual iispection; for leaks will be made periodically ongc i**c '

y-t-.

C \\ ass I,2 %d 3 5f5+e.mS.

The inspection program specified encompasses the major areas of the vessel ASti)E Sec.%s H benxs& die.S.

and piping systems within theg.'i,-.- "...

'..r.-.'.'....

- ~..'. ^. '. '. '. '.. ".. ' _..

^^

^-

r

s..'. a. a.

.,-,,.-...-..2 u,.. s. u.m.-

r, 3

..mu

n...

...3,...

..k.m.

,m,e,t. af P. J.

9'k...-..-

, s... J. 4. m.

,k....

u. n. e.

...J 4,, J 1, 2.

. m A. s. 2 u,- e m.. A. 4..-. v t.. f.

a.

m

...,..4..m,,m.......a.

,,..,,.i.-.....,,.,w.,..-..a..........

.u-..

,u.,_,_

<+

...u,.

n....-....

4.

o_. m._,, _a, m_ _,m.....

r __

i 4.

4.......

.. m_ a,m p.. m,....,...,.. u. s. 4.,. m..a.

4..

. 4. -.... i.....

u.. k.

. i...

u. s.

s. < -. 4...
n...

..._m-.

.,.i.

....i.,_,_,

m_ i.,m

.. i.s

~

w..

4. 2.

2 a k.. m.

6,,6, s-

a..-. s. s..,.-..-2.-.

th... u.. d.. L et.. -.

A. m. 1..

A a r. e m..

.- m 2-

...L.

.w era n Mem The type ofC.:p;; tion planned for each component. depends on location, accessibility, and type of :e-wMa) defect.

Direct visual examination' is pd 4 p ;tc Amendment No. 77,169 3.6-36 RTS-za

~

~'

DAEC-1 x

proposed wnerever possible since itiis f ast and reliaole.

Surface 4%omMWA6 nnectic= are planned where practical, and wnere added sensitivity is i

A Ul tr asonicg.xamMa%6ssting or radiography shall be used where defects can-e required.

occur in concealed surf aces.

Section 5.2.4 of the Vodated FSAR provides details of the inservice inspection program.

Starting with the Cycle 9/10 Refueling Outage, an augmented: inspection s

program was implemented to address concerns relating to Intergranular Stress Corrpston Cracking (IGSCC) in reactor coolant piping made of 'austenitic stainless steel.

The augmented inspection program conforms to the NRC staff's positions set forth in Generic Letter 88-01 and NUREG-0313, Revision 2 for inspection schedule, inspection methods and personnel, andL inspection sample expansion.

i The first 10-year interval for inservice testing of ptsnps and valves in-accordance with the ASME Code,Section XI commenced on February 1,1975 and ended on January 31, 1985. The second 10-year inservice testing interval commenced on February 1,1985 and is scheduled to end. on January 31, 1995.

j The second 10-year testing progran addresses the requirements of the ASME Code,Section XI,1980 Edition with Addenda through Winter 1981, sub. ject to the limitations and modifications of 10 CFR 50.55a. Section 3.9.6.of the Updated FSAR describes the inservice testing program.

l 3.6.H & 4.6.H BASES:

J Shock Suppressors (Snubbers)

Snubbers are designed to prevent unrestrained pipe motion under dynanic loads as might occur during an earthquake or other severe transient, while acconnodating normal thermal motion during systen startup and shutdown. :The'-

~

consequence of an inoperable snubber is an increase in the. probability of, damage to piping as a result of a seismic or other event initiating dynamic loads or, in the case of a frozen snubber, exceeding-allowable stress; limits-ouring system thermal transients..It 'is therefore required that all-snubbers required to protect the primary coolant system or any other safety.

system or component be operable during reactor operation.

Amendment No. JJA,169 3.6-37 RTS-z u

.1

. RTS-261 to NG-94-0389 R

Page 1 of 1 SAFETY ASSESSMENT

)

1.

INTRODUCTION By letter dated May 6, 1994, IES Utilities Inc. submitted a request for revision to the Technical Specifications for the Duane Arnold Energy Center (DAEC).

The proposed changes contained in this submittal which delete reference to the inservice inspection (ISI) program interval dates will allow.

j DAEC's current ISI program interval to be extended in accordance with the ruling in Federal Register 57 FR 34666-dated August 6, 1992.

2.

ASSESSMENT The proposed revision deletes SR 4.6.G.1.a which refers to 1

the ISI program interval.

The proposed revision also adds clarification, deletes the inspection interval dates for the ISI program, deletes reference to the ASME. edition'and addenda requirements to be addressed by the ISI program and j

deletes information that is vague or no-longer necessary from Technical Specification Bases 3.6.G and 4.6.G.

'The j

proposed revision does not involve a significant hazards-consideration.

The changes which delete reference'to the ISI program interval dates are consistent with comparable j

specifications in the Improved Standard Technical Specifications (NUREG-1433).

The ISI program'will continue to conform with the ASME code and approved relief requests.

~

Based upon the above assessment, we conclude that this I

request is acceptable.

.I

'l I

I

5 RTS-261.to NG-94-0389

.i Page 1 of 1 I

ENVIRONMENTAL CONSIDERATION i

10 CFR 51.22(c)(9) identifies certain licensing and. regulatory actions which are eligible for categorical exclusion from the

.j requirement to perform an environmental assessment.

A proposed 1

amendment to an operating license for a facility requires no

)

environmental assessment if operation of the facility in C

ac ordance with the proposed amendment would not:

(1) involve-a significant hazards consideration; (2) result in a significant

')

change in the types or significant increase in the amounts of.any eff]uents that may be released offsite; and.(3) result'in a sigiificant increase in individual or cumulative occupational radiation exposure.

IES Utilities Inc. has reviewed this request and determined that the proposed amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR j

51.22(c)(9).

Pursuant to 10 CFR 51.22(b), no environmental 1

impact statement or environmental assessment needs to be. prepared in connection with the issuance of the amendment.

The basis for this determination follows:

1 Basis This revision meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) for the following reasons:

1.

As demonstrated in Attachment 1, the proposed revision does not involve a significant hazards consideration.

2.

No change in either plant design or operational strategies will be made as a result of this revision, therefore there will be no increase in either the types or amounts of effluents that may be released offsite.

3.

No changes in either plant design or operational strategies will be made as a result of this revision, therefore there will be no significant increase in either individual or cumulative occupational radiation exposure.

4 e

i,+..

a

-

Retrieved from "https://kanterella.com/w/index.php?title=ML20069A996&oldid=4429622"