ML20055B267

From kanterella
Jump to navigation Jump to search
Amend 79 to License DPR-65,reducing Design Reactor Coolant Flow Rate from 370,000 to 362,000 Gpm & Allowable Total Planar & Total Integrated Radial Peaking Factors
ML20055B267
Person / Time
Site: Millstone Dominion icon.png
Issue date: 07/02/1982
From: Clark R
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20055B264 List:
References
NUDOCS 8207210113
Download: ML20055B267 (15)
v • d • e


Text

- - _ _ _ _ - _ _ . _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .

'o, UNITED STATES

!*- 'i NUCLEAR REGULATORY COMMISSION

- ' v, j WASHINGTON, D. C. 20555 yw .- /

NORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY THE HARTFORD ELECTRIC LIGHT COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 79 License No. DPR-65

1. The Nuclear Regulatory Commission (the Ccmmission) has found that:

A. The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee) dated June 18, 1982, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance witn tne Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements '

have been satisfied.

DI:SIO;iATED ORICINA1.

Certified Bh 1 b ot4 &~r&4 L.-

u 82dI210113 820702 DR ADOCK 05000336 PDR

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-65 is hereby amended to read as follows:

(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 79 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is ef fective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Os Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: July 2, ]982 O

e 6

. - . . m .. _w- goe. ..wo-we-.-e- . - -e -.e= m-- .e-- ., - ....,6

ATTACHMENT TO LICENSE AMENDMENT N0. 79 FACILITY OPERATING LICENSE NO. OPR-65 1

DOCKET NO. 50-336 i

4 Remove and replace the following pages of the Appendix A Technical Specifi-cations with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

The corresponding over leaf pages are also provided to maintain document completeness.

Remove Replace 2-2 2-2

! 2-4 2-4 3/4 2-6 3/4 2-6.

3/4 2-8 3/4 2-8 3/4 2-9 3/4 2-9 3/4 2-14 3/4 2-14 a

e k

e 1

,e. ...__..__...

ry ,-_. ,m __, __ - , , , ., _, - _ , , _ _., 7

2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1 SAFETY LIMITS REACTOR CORE 2.1.1 The combination of THERMAL POWER, pressurizer pressure, and maxi-mum cold leg coolant temperature shall not exceed the limits shown on Figure 2.1-1.

APPLICABILITY: MODES 1 and 2.

ACTION:

Whenever the point defined by the combination of maximum cold leg temper-ature and THERMAL POWER has exceeded the appropriate pressurizer pressure line, be in HOT STANDBY within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

REACTOR COOLANT SYSTEM PRESSURE 2.1.2 The Reactor Coolant System pressure shall not exceed 2750 psia.

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

ACTION:

MODES 1 and 2 Whenever the Reactor Coolant System pressure has exceeded 2750 psia, be in HOT STANDBY with the Reactor Coolant System pressure within its limit within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

MODES 3, 4 and S Whenever the Reactor Coolant System pressure has exceeded 2750 psia, reduce the Reactor Coolant System pressure to within its limit within 5 minutes.

MILLSTONE - UNIT 2 2-1

.. . .. . , . ~ . - , . . .

--.7 ...

o O

N w C 2, - =

-x 4s  ;

EN 2

,t y u= O-ue e e 4: c "-

z* - =

3 =

  1. .h t

f'/* $=

0+/g o c

u

\T M =

bu THE RMAL POWF R LIMITE D TO A C $

MAxlMLIM Of 112 OF H4llts gI" g THERMAL Pt)WE R hy T H[ HIGH _ 4 o u.

POWE R L 5 s _ _ -. _ _ _ -- _ _ _E V_i L_T H i l' _ _ _ _ _ _

_ =  !

=-

a E e = '

s =g 5 a <; - : 3s r<= <

1

= 7 v e - z u2 O  :-

A~ z &

l .- : =

l a~ s i 2 3

I  ;

-r - .

l z

.c

o. - -z- -

- a= - -

I do RC CEq *

? y 24e zl

- E_eo c i. -

~

= v. - ~= 1:-

5 i

-l 4N

-e<

f "= -ut -

<3 -

t

=

+1 Ems x

>e.

~z Esse

,=

4

=

, m =z z s =

=1

.g

-s

- vozu. --

z. S-:

.g-

=

e-

-z <c-za=-z-4 zo z

z~ -

=i e -

a-u v- N

-2 m- .5,0z' L

Eg 552, a l

_u  : -

r -

ul u e- u >

z: -<

. t.-e .c .s z- < f.

<1 2 -zo d e w4> a.

u.

I i .

e = =

=

=

=

~

=- c.:

a o

N o o , ,.

F 1 o 3 - aunivuaanal os, a,oa nonixvn MILLSTONE - UNIT 2 2-2 Amendment No. 7, R,B ,79 m + . == w . e,

SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.2 LIMITING SAFETY SYSTEM SETTINGS REACTOR TRIP SETPOINTS 2.2.1 The reactor protective instrumentation setpoints shall be set consistent with the Trip Setpoint values shown in Table 2.2-1.

APPLICABILITY: AS SHOWN FOR EACH CHANNEL IN TABLE 3.3-1.

ACTION:

With a reactor protective instrumentation setpoint less conservative than the value shown in the Allowable Values column of Table 2.2-1, declare the channel inoperable and apply the applicable ACTION statement requirement of Specification 3.3.1.1 until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint .

value.

MILLSTONE - UNIT 2 2-3

TABLE 2.2-1 3

E~ REACTOR PROTECTIVE INSTRUMENTATION TRIP SETP0lN1 LIMITS y FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VAI.UES

[ 1. Manual Reactor Trip Not Applicable Not Applicable

s G 2. Power Level-liigh ru four Reactor Coolant Pumps < 9.6% above TilERMAL POWER, < 9.7% above TilERMAL POWER, with Operating with a minimum setpoint of a minimum of < 14.7% of RATED

< 14.6% of RATED TilERMAL TilERMAL POWER, and a maximum of POWER, and a maximum of 3,106.7% of RATED TilERMAL POWER.

< 106.6% of RATED TilERMAL POWER.

3. Reactor Coolant Flow - Low (1) m four Reactor Coolant Po ?s > 91.7% of reactor coolant > 90.1% of reactor coolant flow E Operating flow with 4 pumps operating *. with 4 pumps operating *.
4. Reactor Coolant Pump > 830 rpm

> 823 rpm S*_ed - Low

. Pressurizer Pressure - liigh ,

3.2400 psia 3,2408 psia

. 5. C- .ainment Pressure - High 5,4.75 psig 5,5.23 psig R /. Staam Generator Pressure - ~> 500 psia -> 492 psia 2 Low (2) (5)

A i

= 8. Steam Generator Water > 36.0% Water Level - each > 35.2% Water Level - each steam Level - Low (5) steam generator genera tor h' 9. Local Power Density - liigh (3) Trip setpoint adjusted to not Trip setpoint adjusted to not

s. exceed the limit lines of exceed the limit lines of

!* Figures 2.2-1 and 2.2-2-(4). Figures 2.2-1 and 2.2-2 (4).

R M

Design Reactor Coolant flow with 4 pumps operating is 362,600 gpm. ~

8

1 1

i O

'~ ' ' ' ' ' I I .;l : ,l ..]

,sj;;.'== j. .

--a_-._ . . _ _ . . ._ __

i  ! ,- -). _ .=; }.g=.4

,E

=.{ =_=. = l .

e

. . N u

-.. - . . _ _ _; I

l. .;;., j.. -

I '

' j. ~~.......;. O

  • -t g

~f ; : !.

._ _j , ~ ~ .

m O

w

' '.l .t w a o

o = ca

" U g &

o w

!df u.

5 g U C i y . =. . . j e w a

! -i m o .c

--i 2 O

~l- _

a g

3 >= m

~

-. } Q i . m

. - .1 e 3 g

  • O u.

- . : . . . . ._ q _. . . .

. i- :! c:

~ . . . _ . . _

. j . _; . . w -y w

O ce z

E e m

.g.. e 5, o 2 4

. . . . . . r q

R

  • m
  • - ~
__ CC D

C C

o e o I 8 S e

~ 2 g

o. o. 5 8 o o a

- - - a - - a SUO13Vd NOl1V1N3WDnv MILLSTONE - UNIT 2 3/4 2-5 Amendment No. 38. 52, 61 1

I l

1 POWER DISTRIBUTION LIMITS TOTAL PLANAR RADIAL PEAKING FACTOR - F LIMITING CONDITION FOR OPERATION 3.2.2 The calculated value of F ,definedasFfy=F (1+Tq ), shall be limited to < l.583.

l APPLICABILITY: MODE 1*.

ACTION:

4 WithFfy>l.583,within6hourseither: l

a. Reduce THERMAL POWER to bring the combination of THERMAL POWER l

andF[j to within the limits of Figure 3.2-3 and withdraw the full length CEAs to or beyond the Long Term Steady State Insertion Limit of Specification 3.1.3.6; or I, b. Be in at least HOT STANDBY.

SURVEILLANCE REQUIREMENTS 4.2.2.1 The provisions of Specification 4.0.4 are not applicable.

4 2.2.2 Ffy shall be calculated by the expression F =F (1+Tq ) and F shall be determined to be within its limit at the follcaing intervals:

xy r

a. Prior to operation above 70 percent of RATED THERMAL POWER after each fuel loading,
b. At least once per 31 days of accumulated operation in MODE 1, and
c. Within four hours if the AZIMUTHAL POWER TILT (T q ) is > 0.02.

See Special Test Exception 3.10.2.

3/4 2-6 Amendment No. 38,42,79 MILLSTONE - UNIT 2

' '* m . m. ,, , , _ _

POWER DISTRIBUTION LIMITS SURVEILLANCE RE0UIREMENTS (Continued) 4.2.2.3 F xy shallbedeterminedeachtjmeacalculationofFfy is required i by using the incore detectors to obtain a power distribution map with all full length CEAs at or above the Long Term Steady State Insertion Limit for the existing Reactor Coolant Pump combination. This detenninatica shall be limited to core planes between 15% and 85% of full core height inclusive and shall exclude regions influenced by grid effects.

4.2.2.4 Tq shallbedeterminedeachtimeacalculationofFfy is required i

and the value of Tqused to determine F xy shall be measured value of Tq .

l l

l MILLSTONE - UNIT 2 3/4 2-7 Amendment No. 38

x p

i,

.i' it f @'

U i :lll 't j[ li!' j,y p 'l. ,;

'i i

i li d(iyI

, l3 -,[ d

'In

'i l h i I

j ,jj: i,

, l T r- (1.583, l~ P --  :! --

!:- UNACCEPTABLE

1. 0),'. p j,p ' ' ' ,

-l l il tji,i r- il!i Hli lll:

,1.

llll !jll !h OPERATION olil ..

(1.62 3, .975):; . iF xy Limit Curve l t

9 p;

m w 1.0 .l' h (1.59 7, 1.0) .

REGION i

I i

$ .p l'! .ih Ihf T ,'

l l iL 'ii. Hl ;i (lv

!h !:5 il a.

> !+

.I il l jd 1"l 3.{ l.' --

, I g .2 1 p 3jl

... .l.ll.l:j:l: ,%

Q ,,-li (1.626,.86) l - l%

.i

(1.678, .8725), l l

M [ M.I'h_M 1, .90)! q mI!I'j(1.655, ll . - N N l

i N w 0.8 ,-

' p' I N I . H .

! ., y .  ;, i-A' . R i~. I I .(1.683, .755) .(1.74,

.8025) y 4li I p"[h,; !j

'.lI l ,ll l. N

{ @ ,: : \

$  !!' j! i l i ,

i i.i I )

ci i j. if {

- 1' a E " t N.  !

I l ' " p' Limit Curve 5

u-O 0.6 l,

. .li,

', M lsi-fi il, l"

e ' f'.h

( hF r I i -

i O.74, .675) i lj. ' '

.n; p- -

a, .,

, , 1:

1 ,

I i- i 8  ; , ,

c: .'! n ,,

ii ,

,. T In::

l ,

E i,

]. p re ,1,' ili "I /' ]l i l l l

u s , .

j j ,

'!I. ;iI

[ [ .! I  ! ' ' l l l'i i

nq I.

) [

R4 T,' j,iOPERATION ACCEPTABLE REGION l- g ' '

g .J' p !! 7 R ,!g :j.:' y 'n m

En j j'

}i' i j; .,l. t 'i

U j, ' . . ,'

iL

~,

!' ~

'j ~ '

l j l o i i ';

". l p:< 'l -

I-.  ;;.

o i

.2 , }. .p ji -l i i a p iji.

f a2

'. jq y , p y ,

i j

l'3 '

I ?l h -

M +

,:r ,,

l i

f.

' i

. ;l ,

!j ti i. i 2 l l 1-  : -

,:  ?.- - :6 l g

1

,i, ' , e , j I l ,

to 00.

Aa 1.57 .

1 59 1.61 1.63 1.65 1.67 1.69 1.71 1.73 1.75 1.77 T

$ F,T ; p xy IF , x (1 + T y l : F ,y n (1 + T q ll ,

=

O

  • w

. FIGURE 3.2-3 Total Radial Peaking Factor Versus Allowable Fraction of RATED THERMAL POWER rn N

e 4

6 9

POWER DISTRIBUTION LIMITS T

TOTAL INTEGRATED RADI AL PEAKING FACTOR - F, LIMITING CONDITION FOR OPERATION 3.2.3 The calculated value of FT , defined as FT y

, pr (1+Tq ), shall be 7

limited to < l.597. l APPLICABILITY: MODE 1*.

ACTION:

With FT7 > l .597, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> either: l

a. Reduce THERMAL POWER to bring the combination of THERMAL POWER and FT7 to within the limits of Figure 3.2-3 and withdraw the full length CEAs to or beyond the Long Term Steady State Insertion Limits of Specification 3.1.3.6; or
b. Be in at least HOT STANDBY.

SURVEILLANCE REQUIREMENTS 4.2.3.1 The provisions of Specification 4.0.4 are not applicable.

T 4.2.3.2 FfshallbecalculatedbytheexpressionFf=F(1+T)andF r q y shall be detennined to be within its limit at the-following intervals:

a. Prior to operation above 70 percent of RATED THERMAL POWER after each fuel loading , -
b. At least once per 31 days of accumulated operation in MODE 1, and
c. Within four hours if the AZIMUTH L POWER TILT (T q

) is > 0.020, T

4.2.3.3 F shall be determined each time a calculation of F is required r 7 by using the incore detectors to obtain a power distribution map with all full length CEAs at or above the Long Term Steady State I,nsertion Limit for the existing Reactor Coolant Pump Combination.

T 4.2.3.4 T shall be determined each time a calculation of F is required q

and the value of Tq used to detennine Frshall be the measured value of 2-

  • See Special Test Exception 3.10.2.

MILLSTONE - UNIT 2 3/4 2-9 .....ent No. 18, ,

3

~. . .- . . . . . . - . - . ., . . . . . . . __ - .-

POWER DISTRIBUTION LIMITS AZIMUTHAL POWER TILT - T q LIMITING CONDITION FOR OPERATION 3.2.4 The AZIMUTHAL POWER TILTq (T ) shall not exceed 0.02.

APPLICABILITY: MODE 1 above 50% of RATED THERMAL POWER *. l ACTION:

a. With the indicated AZIMUTHAL POWER TILT determined to be > 0.02 but < 0.10, either correct the power tilt within two hours or determine within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and at least once per sub-sequent 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, that the TOTAL PLANAR RADIAL PEAKING FACTOR.(F,T y )

and the TOTAL INTEGRATED RADIAL PEAKING FACTORr (F ) are within the limits of Specifications 3.2.2 and 3.2.3.

b. With the indicated AZIMUTHAL POWER TILT determined to be > 0.10, operation may proceed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> provided that the TOTAL T

INTEGRATED RADIAL PEAKING FACTOR (F7 ) and TOTAL PLANAR RADIAL PEAKING FACTOR (Ffy) are within the limits of Specifications 3.2.2 and 3.2.3. Subsequent operation for'the purpose of measurement and to identify the.cause of the tilt is allowable provided the THERMAL POWER level is restricted to < 20% of the

' maximum allowable THERMAL POWER level for the exisBng Reactor Coolant Pump combination.

! SURVEILLANCE REQUIREMENT -

l~

4.2.4.1 The provisions of Specification 4.0.4 are not applicable.

4.2.4.2 The AZIMUTHAL POWER TILT shall be determined to be within the

!- limit by:

a. Calculating the tilt at least once per 7 days when the Channel High Deviation Alarm is OPERABLE, -

l' l

See Specia! Test Exception 3.10.2.

l MILLSTONE - UNIT 2 3/4 2-10 Amendment No. g ,52 l-

-,-.y,, . - . . . _ . . _ . . _ . _ _ . _ _ , _ _ _ _ . , ,

l l

l POWER DISTRIBUTION LIMITS DNB MARGIN LIMITING CONDITION FOR OPERATION 3.2.6 The DNB margin shall be preserved by maintaining the cold leg I temperature, pressurizer pressure, reactor coolant flow rate, and AXIAL SHAPE INDEX within the limits specified in Table 3.2-1 and Figure 3.2-4 APPLICABILITY: MODE 1.

ACTION:

With any of the above parameters exceeding its specified limits, restore the parameter to within its above specified limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to < 5% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.2.6 The cold leg temperature, pressurizer pressure, reactor coolant I flow rate, and AXIAL SHAPE INDEX shall be determined to be within the limits of Table 3.2-1 and Figure 3.2-4 at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

IIILLSTONE - UNIT 2 3/4 2-13 Amendment tio. 38 i

e TABLE 3.2-1 DNB MARGIN d

LIMITS

/

Four Reactor Coolant Pumps Operating /

Parameter Cold Leg Temperature < 549'F Pressurizer Pressure t 2225 psia

l AXIAL SHAPE INDEX Figure 3.2-4

  • Limit not applicable during either a THERMAL POWER ramp increase in excess of 5% of RATED THERMAL POWER per minute or a THERMAL POWER j step increase of greater than 10% of RATED THERMAL POWER.

i I

.4 MILLSTONE - UNIT 2 3/4 2-14 Amendment No. -)$, ji/,79 i .

f w c;-+% - -w.- ge,e.., ., , ., . , , , . , , , , , , . , , , , , , , , ,

__ ________f_

Retrieved from "https://kanterella.com/w/index.php?title=ML20055B267&oldid=3638080"