ML20215K241

Proposed Tech Specs Revising pressure-temp Limits & Max heat-up & cool-down Rates for RCS

ML20215K241
Person / Time
Site:	Millstone
Issue date:	10/20/1986
From:	NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20215K238	List: B12224, Application for Amend to License DPR-65,changing Tech Specs to Revise pressure-temp Limits & Max heat-up & cool-down Rates for Rcs.Fee Paid ML20215K241
References
TAC-63133, TAC-63198, NUDOCS 8610280067
Download: ML20215K241 (4)

Text

. _ _ _ _ _

Docket No. 50-336 Attachment 1 Millstone Nuclear Power Station, Unit No. 2 I Proposed Revisions to Technical Specifications Pressure-Temperature Limits 4

October,1986 kod kOOCK67 861020 P 05000336 PDR

REAC'IOR COOLANT SYSTEM 3/4.4.9 PRESSURE / TEMPERA'IURE LIMITS REAC'IOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION 3.4.9.1 'Ihe Reactor Coolant System (except the pressurizer) tenperature and pressure shall be limited in accordance with the limit lines shown on Figure 3.4-2 during heatup, cooldown, criticality, and inservice leak and hydrostatic testing with:

a. at A

ormaximum below 110heatup F, 30 of 20*F F in anyinone anyhour one hour period period with with T T,P a c_ i below 140 F and above 110 F, and 50 F in any one hEdd period '

with T,y, above 140 F.

b. A maximum cooldown of 80 F in any one hour period with T,,'

above 300 F and a maximum cooldown of 30 F in any one hour period with T at or below 300 F and above 200 F, and 20 F in any one ho'd' period with T,y, at or below 200 F.

c. A maximum temperature change of 5 F in any one hour period, during hydrostatic testing operations above system design pressure.

APPLICABILITY: MODES 1, 2*, 3, 4 and 5.

ACTION:

With any of the above limits exceeded, restore the temperature and/or pressure to within the limit within 30 minutes; perform an engineering evaluation to determine the effects of the out-of-limit condition on the structural integrity of the Reactor Coolant System; determine that the Reactor Coolant System remains acceptable for continued operations or be in at least Ier STPRDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce the RCS T and pressure to less than 200*F and 500 psia, respectively, within the fol b ing 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

• See Special Test Exception 3.10.3.

i I

3/4 4-17 l

MILLS'IONE - UNIT 2 Amendment No. #f, %

j

- - . - , , - v-,

x p_ . ___. y__. _;, _ _ . _

z_.,--.. __

~

..' ] ,

__=.

- - - _ . = .- := . --:---

- ~ - -

- " ~ _.._L... . _ _ 'uM ie:,m a h Te2 9 --

-- - -4 .--- . -

-~= r -

. . , r-- - --

,- - .; - s__

=-: '- -f..==r-,=. g:'.a.. an ag.g g g ,.. eerf tteEnf -- E -  :- *T. + --1.- .:L

--- - . . . . . . =..... .._a__. . i ._ i- -- . r .- : - -

--i n - : 1-

- NmHrsey senarpse amnv TTwTeneTrure: wrue 19 yrrir vrwyn Trnt: -  :-

_ a ~ f i_- OMN 15 ~-M;-i 55

=== u-~Ii'.J n

=T~~h i__ ..M;n:u: .:_My

- ~~ ^ - ' - - ' - - --

~~

iiEL - - - - -

' C 4=

3200

~~~~

~~~ ~~ -

ii; 22x2EZ' ~ En =: ~ 7STSTF.L"E?EtE ii rik =4-- ,i ~

_.__n:-2

'MDSTADh=r y _a . .n m..

- ---- n. _. n...-...^__.7_._.:.-__._ ._

7 7---xx; =r_ ;;g_ :=-

.ggg

=

_, . .-_JM_;_. _^=~E T=_ ~

==i- _ . . . _- 7:=3~2E ^ ~=tE  :  : L.

g _ _ _ , _ _ _ . _ __ . _ _ _ . , . _ . . _ .. __. _ ._ _

___.;~-. ..y_

d=.= - -=. --1 : -- .

__,= - _..

-1EL-

_ ._- _.- _-= . - _ .

~ l-10,0030_65-3. - . T . ,_ W.12GT _ _ . _- : .; L

^-~~

^^

._-i$'$$5$bnEm -= . .

K ~5~.5$ ^_ ~:

7 2400"M -- -.-- - -

gg= - -

r-- --

3

=-- - - - --- -- --

y_ , _ , _ - __ __

j  :---r---l . _ . -

w _ =s ---

~3 3 ;__- ;

l- ~

,a __. .--

-_T:Z = >_ q? -~ '1_

h2000 y

M, _ . . ._h..

,= . _ .

g lEI$'sf*'~- - _-_ _ i1 [=G:k_.. _.AS~

, a xey_=y =a =,=wa= -

_fgg ==.= =_ __ _,

- - =:=== 343g:,._

~ ~.2ZZU

" 1600

• -4 ,8'i/N'$ sc -=- ~ -

• E1 --

._,g=siL_m _f ,_.

, _:_,-_=_ F'"_--- -.__..-._a____ , -

~ ..

g _ _.__ __

g -- :_ -

lgf--l -- ___ = g g-

=_.-:,..- 72

_ _ _ _- * ~ ~ _,-

Q

,.,12oc

_' ~~~~, _~51, _td- _._-

==.2

(_

-/.---p_Eym :

2, y

. =___.~t._._4._._. .___- -

u m-  : r- -,

g _

_/= -n = 1--~-If_ _L 2 ~'____ _ _ _ _ . . - _ _

y _-_-

j '-- ,M_ qq -D -.- -

2..,._T. f

'_0PRRA*I(W ~~[ ~

g _._ ',_

=j_ ---f _

r_.,.-_

y

-+-

7 ,

400 _..a __ _

_t- ._

culIIKIs.wmsums, o . +

.pggggy _-_ ._ . ___._e.

=_

-_-.2__... .

C 10 100 200 500 400 500 600 IEICATD REA0 TOR COOLANT TDGERAl"JRL T, , D I

l I

l i

l l

Figure 3.4-2 Reactor Cbolant .9ysten Pressure 'maperature Limitaticas for 12 Full Power Years l MILLS'KNE - IJNIT 2 3/4 4-19 Amendment No. [ [

\

L

! REAC'IOR COOLANT SYSTEM BASES he heatup and cooldown limit curves (Figure 3.4-2) are composite curves which were prepared by determining the most conservative case, with either the inside or outside wall controlling, for any heatup or cooldown rates of up to the maximums described in Section 3.4.9.1. The heatup and l cooldown curves were prepared based upon. the most limiting value of the j

. predicted adjusted reference temperature at the end of the service period

} indicated on Figure 3.4-2.

We reactor vessel materials have been tested to determine their

the results of these tests are shown in Table 4.6-1 of the initialSaft

Final RT E[ Analysis Report. Reactor operation and resultant fast neutron l irradiation will cause an increase in the RT,3,. %erefore, an adjusted I reference temperature, based upon the fluence, can be predicted using the

! methods described in SECY-82-465 "NRC Staff Evaluation of Pressurized i hermal Shock", November, 1982. Because it is more conservative, this j method was used rather than the proposed Revision 2 to Regulatory Guide 1.99.

We heatup and cooldown limit curves shown on Figure 3.4-2 include predicted adjustments for this shift in RT,,, at the end of the applicable service period, as well as adjustments for possible errors in the pressure and temperature sensing instruments.

l he actual shift in RT of the vessel material will be established

periodically during operati,o,n, by removing and evaluating, in accordance ,

with ASm E185-73, reactor vessel material irradiation surveillance 1 specimens installed near the inside wall of the reactor vessel in the core area. Since the neutron spectra at the irradiation samples and vessel inside radius are essentially identical, the measured transition shift for ,

a sample can be applied with confidence to the adjacent section of the j reactor vessel. The heatup and cooldown curves must be recalculated when the ART determined from the surveillance capsule is different from the

calculaEed ART,,, for the equivalent capsule radiation exposure.

We pressure-temperature limit lines shown on Figure 3.4-2. for reactor criticality and for inservice leak and hydrostatic testing have been provided to assure compliance with the minimum temperature requirements of l Appendix G to 10 CFR 50 for the reactor criticality and for inservice leak and hydrostatic testing.

We maximum RT,,, for all reactor coolant system pressure-retaining materials, with the exception of the reactor pressure vessel, has been determined to be 50 F. The Lowest Service Temperature limit line shown on since Article NB-2332 (Sununer Addenda Figure 3.4-2 is based upon this RT, ISME Boiler and Pressure Vessel Code of 1972) of Section III of the requires the Lowest Service Temperature to the RT,,, + 100*F 1

B 3/4 4-6 MILLS'10NE - LEIT 2 Amendment No.,9(,

i

, ,r g, - -- w~, - - , , -