ML19322E321

From kanterella
Jump to navigation Jump to search
Amend 48 to License DPR-36,supporting Operation at Full Rated Power During Cycle 5
ML19322E321
Person / Time
Site: Maine Yankee
Issue date: 03/07/1980
From: Reid R
Office of Nuclear Reactor Regulation
To:
Shared Package
ML19322E317 List:
References
NUDOCS 8003270178
Download: ML19322E321 (15)
v • d • e


Text

-

py 0,

UNITED STATES

[

."4,.

f I, NUCLEAR REGULATORY COMMISSION c

, +g j

s,o.Ja)#',i

'*%SHING TON. D. C. 20555 ri r

g

-.=j MAINE YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-309 MAINE YANKEE ATOMIC POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 48 License No. DPR-36 1.

The Nuclear Regulatory Commission (the Comission has found that:

A.

The application for amendment by Maine Yankee Atomic Power Company (the licensee) dated December 5, 1979, as supplemented February 15, 1980, 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 conformance with the applicatio:,

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 with the 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 regulationsand all applicable requirements have been satisfied.

1 8003270

.g 9

. i 2.

Accordingly, the license is amended by changes to the Technical

~

Specifications as indicated in the attachment to this license amendment, and paragraph 2.B.(6)(b) of Facility Operating License No. DPR-35. is hereby amended to read as follows:

(b) Technical Specifications The Technical Specifications contained in Appendix.

A, as revised through Amendment No. 48 is hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendaent is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION A

l' Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors

Attachment:

Changes to the Technical Specifications Date of Issuance: March 7,1980 l

l l

-. - - ~ ~ ~

33;

ATTACHMENT TO LICENSE AMENDMENT NO. 48 FACILITY OPERATING LICENSE NO. DPR-36 DOCKET NO. 50-309 Revise Appendix A as follows:

Remove Pages Insert New Pages 2.1-1 2.1-1 2.1-4 2.1-4 2.1-5 2.1-5 2.1-6 2.1-6 3.10-1 3.10-1 3.10-2 3.10-2 3.10-3 3.10-3 3.10-4 3.10-4 3.10-10 3.10-10 3.10-11 3.10-11 3.10-12 3.10-12 3.10-13 3.10-13 3.15-1 3.15-1 e

,,c...

2.1 LIMITING SAFETY SYSTEM SETTING - REACTOR PROTECTION SYSTEM Applicability:

Applies to reactor trip settings and bypasses for the instrument channels monitoring the process variables which influence the safe operation of the plant.

Objective:

To provide automatic protective action in the event that the process variables approach a safety limit.

Specification:

The reactor protective system trip setting limits and bypasses for the required operable instrument channels shall be as follows:

2.1.1 Core Protection a) Variable Fuclear Overpower

<Q + 10, or 106.5 (whichever is smaller) for 10<Q<100

<20 for Q<10.

where Q = Percent thermal or nuclear power, whichever is larger.

b) Thermal Margin / Low Pressure

>A QDNB + BTe + C, or 1835 ps,ig (whichever is larger) where T = cold leg temperature, OF e

A = 2004.3 B = 17.9 C = -10053 QDNB = At x QRt l and QRg are given in Figure 2.1-la and 2.1-lb, respectively.

A This trip may be bypassed below 10 percent of rated power.

c) The symmetric offset trip and pretrip function shall not exceed limits shown in Figure 2.1-2, for three loop operation. This the trip may be bypassed below 15 percent cf rated power.

d) Low Reactor Coolant Flow 293 percent of 360,000 CPM (3 pump operation)

This trip may be bypassed below 2 percent of rated power.

2.1-1 Amendment No. 29, 3$, J9,48 L.

o

^

. r. :.-. s... : 3". __9. ". T:- E...i. :.i _.=. :".. - h..2... :._. : :.-~ -___... =..=.. :.".. i

.- ' = " " = _

~~

. - 4 ;* =; *f.= ;.= ** _ _.. *

'* * =i n.21 T."';... '.* _....J._

7_...

_;=a :,-.,_.:;.; _,; %.. ' _

?! -

::- * *T-' :4 7* :-.- -:. ~ T : : - ' *. ' :-' ' '-
T
  • !'=...__

U1'.'_..

A _-

_.._..___;;":"*;**'**'--.~.~_**=~.*.':,,s'.

        • "I--

_....._...:*.:--=...._....;:..:*""".-**-~~.4.0'a=*.*..

'F

.' ' ' '. * * \\. : ;; ? *,-- ; L...";;;. ; 1;; ~ ;. t:--**

-,,-.:L* r, =- * *- 7 "..

J

.. n ;..'- *

!. : 7 **. : '

_\\:".=_;.C.;..:;;. :: :.'7 ' -. r. -T : ' 274.;.._.. *_ ; -.,

.4:"

2 T.~

F.==__.'._..=-.J

,;l".
.;;.**. -""== J.'..~ 1 '.; " ".. *J:.? * *" * ' * **.*: L ! * * * * *:1.

~

.._..-:.==____.

v.--

... _ _:= _ _ _.__._ x _. _ _ _...___ _ _ _ __._.

.*r---

;.y. - - - -. - - _y;--- -

____. - - - _ _ - _ =

..__......_.P.2-*;._":.___J'_"J**.*.."_N

.T ; *

  • M Z,. ' J 4;' '
  • ;l.Z*--

7

'. ""* :: r.: 7 =: -"-l'L-J

.__==7.V.-

    • .,._..r.\\. _ _ _.. _ _ _.. _ _-.. T -~1 ?: 7. *? -~1.

~ - ---' *

..._7P*!*""*.~

-5l;5 5.

._-Q,,~: =_.f --"1

~. _ - _.. -.

q ;,.;'* -~" _-*- 5

.g _

'*---?L.._ =

=~

_., _.,. ; _ !_.:.:. :. =..=.

.- _- --. _.; _;.\\.-- : : = =._._...

r 7 :=_ ::.:.' ' ::: '_ (

g g

n

~*

O

!==

  • ": = ;._ _

.'\\r.,. ::".._ _ ' ' ~ ~ ; 72;; =.. : L".J :...~.~_J;'.:.:*"-*.~."*"_._ _.' :

  • JG; ;..!"

-~.-*:""2".**.*"".*

..N : - '"..:_ :..; *J.- o *

..._'~._..__:=._.=~.:".:*...?;!*7._._..... ;:-"'".*"*'***

1 g

~.

c =*T.-

_ :. : L ' --- '.=

_ ;;.4:_.

- \\.

4--

. = :. -.:-='

"..... _ _ _ _ 4 t-._ __.._: -

s______

M N-b h.

=1.:=2.:.:

- :. _ _== : :=

..i*;*.****-***

a

  • ' ! **J". !

$==.=--"__..-----:w"*J"*"*:___.

._ -- * =:.:::

=

-g

=_ -.=..:::..;._.

==

'7

==L_ _.

.. 1: -.. _

a.

,m o

o

=

===_... _.--

.= _s.- :: _:: -- --. ; - *

..J.,7.._._._._=_

E.._._.____.__

___,_g.=._...=:._.:=._..-.,._

g

_..__s_

,q:

- = =.5._

a C

- := : _ =- =__

y s

7.=_2'--: = r.=== -

t-y g

O'.

o

. : nu== rr ---

--== -. -== 2 e

,.____.__.:_==_=.:.:.... _.

m

-== -a N

-=.

.,:=a.===..-=_

--=2.

o

u---

-- _. _ _.J:

===:==.

u

. _ = -

......... _ _ _:22__2.:._=_ _ _

2__2._-=.=.._.:.=-.

c4 O

W

+

s e

o a

e 4

___ _ y z

w

-::=___._.=_

_ _ =

_=---:..__._.--/

u o

c

.. ::-----.2._

m. -

i u

n..2 _== := /

O'

-. _. _ _ _... _ _ - - e e

g 3

. _ _ _g __ __ _._;.. u ;;/_;.:.

g

________ __.___._ _ =

r-m y

__ m g

. W-5E3i*":#!:"'

f_

4 555.E

-T- ~ ::"

N M

o m

H o

3

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

-- as

>.-- _ _:--/ : -

zg n,

-3

... = - - -

o 1--

=-.--:-1=_=.

as au g

n m

o

_ ~ _ _

___:=

--_./.__.=_

m un u a>

e f'..

m E3[-/;,.~.'~2 U

O' N

3.U_E ~: --*C.==._ ~.__._.== __.

- g g

.__------:------------==

=;._ = f._; ; ;.- r

= m

.,a,

?'*_;":?*"~*--*r"*-*--

.i.(

.'**/*:.____.

  • * * =.: *L :==~g -- _ __"r". _. _,: :;;; ;,0 - = '----*

Q g

4 C

4 I"*

.. =.....

=
r j "- ;:=74; -._

- ;;.:= 4,;,4:

~4

... _ _ _..._..___.=:==.=---__=:_z

.= : - -

=* _.

  • 1"".*

g

. "_O = * :'- * !? ;.: -- * --

=..=_:..- :: _ =.

9.,

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

4

= * :..J

,
:. C

.r. _--._--".r_t_.:::::.;... __*._....

g

.n. u.,.; ;. _ _ _.... _..... _. - : r_ =_ =_ :.... - _..

h ___ = :: _

3 1.

-- ;_..... - - - -" 4:r :--J=" ** P. *

.i--'* :.";-~~~'

  • * {" !! *.* **7. : : ";* :.--* =. ::: -" - r:-- - ""* ;,;;.: :P. ! ": 4. " ! ~

i I

.-.~. -. - l : :-- =: :.- - - : -. - -: -. : u - -. = : r.~/. = :-- *- "-- * * ~

. T.. ? * "* P. : = =

2.*--

T.: _7:,, 7,,,;;;.*; -....... :- 7._..... ;. C*TT

. - r :.-. _.

c

...=...=....=.=_._=_._=.__---._;_=...=__=__.=.._._..:-=:l._.u....

": r..:..

- ~:::::...... _

1 o

o o

o e

o o

N N

o o

E.,, u",. I ~6.L A",=

~

Thermal Margin /'.,cw Pros 3urc Trip f ' coin't.

F,iqurc yam vc" sus 6.1-10

--w ps'...ed.: w.

~.,e

.-wn

.w (no,a. versus n.t) 2,1-4 y=

U Amendment No. U, M, H, 48

Where: A x QR

=Q g

g DNB and pt rip = 2004.1 y

+ 17.9 T

- 10051 var DNB in T

= Cold leg temperature in 1.2

-- /

1.0 1,0--

n l

l

.8

.82 --*-

1.0 A

.70 QRg

.6

.4 e.25

.2 00

.2

.4

.6

.8 1.0 1.2 Fraction of Rated Thermal Power g app O'O 3'T

[

6eS 6

3 MAINE YANKEE Thermal Margin / Low Pressore Technical Trip Setpoint Part 2 Figure Specifications (Fraction of Rated Thermal Fuwer versus QRg) 2.1-lb 2.1-5 Sendment No. 29, 38, 40, 48

j n

1 120 110 A

/

N

/

100

/

\\

/

\\

90

/

\\

2

~

/

\\

80

\\

/

e di

.\\

'l

\\

?

70 I

~ TRIP LIMIT I'

l w

l' l

g 60 u

8 l-6 I

50 l LCO PRE-TRIP ALARM

\\

_i i-40 l

li l

It

~

l 30 t

..l.

l g

i i

i 20 l

.6

.5

.4

.3.2

.1 0

.1

.2

.3

.4

.5

.6 Symmetric Offset =

+B p@@@ @$$bb l

l MAINE YANKEE Symmetric Offset Function. Three Pump Operation Figure i

Technical 2.1-2 Specification 2.1-6 Amendment No. 29, 38, 48

e 3.10 CEA CROUP, POWER DISTRIBUTION, MODERATOR TEMPERATURF COEFFICIENT LIMITS AND COOLANT CONDITIONS Applicability:

Applies to insertion of CEA groups and peak linear heat rate during operation.

Objective:

To ensure (1) core suberiticality after a reactor trip, (2) limited potential reactivity insertions from a hypothetical CEA ejection, and (3) an acceptable core power distribution, moderator temperature coef ficient, core inlet temperature, and reactor coolant system pressure during power operation.

Specification:

A.

CEA Insertion Limits 1.

When the reactor is critical, except for physics tests and CEA exercises, the shutdown CEA's (Groups A B and C) shall be fully withdrawn.*

l 2.

When the reactor is critical, except for physics tests and CEA exercises, the regulating CEA groups (1 through 5) shall be no further inserted than the limits shown in Figure 3.10-1* for 3 loop operation.

3.

When the reactor is critical, the available shutdown margin with one CEA stuck out will not be less than 3.2% in reactivity. During low power physics testing at the beginning of a cycle, CEA insertion is permitted such that the minimum shutdown margin is no less than 2% in reactivity.

4.

Operation of the CEA's in the automatic mode is not permitted.

  • NOTE - CEA's shall be considered fully withdrawn when positioned such that rods are inserted within 4 steps fruin their upper electrical limit.

B.

Power Distribution Limits 1.

The peak linear heat rate with appropriate consideration of normal flux peaking, measurement-calculational uncertainty (8%), engineering factor (3%), increase in linear heat rate due to axial fuel densification and thermal expansion (0.3% for Types E,C,H&I only) and power measurement uncertainty (2%) shall not exceed:

3.10-1 Amendment No. 29, 33, 49, 48 L

11. 5 k w/ f r f > 0. 50 and CAB $ 792 MWD /*1T Type I:

L f > 0. 50 and CAB > 792 MWD /MTU 14 kw/ft 16kw/ftf30.50 Types E,C,H,&I:

14.0kw/ftf>0.50 16.0kw/ftf$0.50 where f is fraction of core height and CAB is cycle average burnup.

Should any of these limits be exceeded.

imediate action will be taken to restore the linear heat rate to within the appropriate limit specifed above.

The total radial peaking factor, defined as Ff=F l

2.

R (1+Tq). shall he evaluated at~ least once a month 4

during power operation above 50% of rated full power.

P 2.1 F is the latest available unrodded radial l

R peak determined from the incore monitoring system for a condition where all CEA's are at or above the 100% power insertion limit.

T is given by the following expression:

q (Pa-Pc)2 + (Pb-Pd)

T

=2 9

(Pa+Pb Pe+Pd)

+

3 Pi = relative quadrant power determined from incore system for quadrant i.

when the incore system is operable and by Specification 3.10.B.4 otherwise.

i T

2.2 If the measured value of F exceeds the R

l -

value given in Figure 3.10-4, perform one of the following within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, i

l a) Reduce symmetric offset pre-trip alarm and trip band (Figure 2.1-2), thermal margin / low l

pre ss ure trip limit (Figure 2.1-1 and Tech.

l Spec.,2.1), and Excore LOCA monitoring limit I

F (Figure 3.10-3) by a factor 1 " ***""'*d rg (Figure 3.10-4) or P

. e.d. _

.,,....,,, e i

+

b) Reduce THERMAL POWER at a rate of at least 1%/ hour to bring the combination of TRERMAL power T

and

  • increase in F R

3.10-5, while maintaining CEA's at or above the 100% power insertion limit; or c) Be in at least 110T STANDBY.

3.

Incore detector alarms shall be set at least weekly.

l Alarms will be based on the latest power distribution obtained, so that the peak linear heat rate does not exceed the linear heat rate limit defined in Specification 3.10.B.1.

If four or more coincident alarms are received, the validity of the alarms shall be immediately determined and, if valid, power shall be immediately decreased below the alarm setpoint.

3.1 If the incere monitoring system becomes inoperable, l

pi r f onn ini.- of I Im followinn within 4 E.F.P.II.

a) Initiate a power reduction to (P at a rate of at least 1%/ hour where P(% of raced Power) is given by:

P = 0.85 (Linear heat rate permitted by Specification 3.10.B.1) x 100 Latest measured peak linear heat rate corrected to 100% Power while maintaining CEA's above the 100% power insertion limit and monitor symmetric offset once a shift to insure that it remains within + 0.05 of the value measured at the time when the above equation is evalvated. This procedure may be employed for up to 2 ef fective full power weeks, or b) Comply with the alarm band given in Figure 3.10-3.

If a power reduction is required, reduce power at a rate of at least 1%/ hour.

4.

The azimuthal power tilt, Tq, shall be determined prior j

to operation above 50% of full rated power af ter each refueling and at least once per day during operation above 50* of full rated power.

Tq is given by the following expression:

(Da-Dc)h(Db-Dd)

Tq = 2 (Da + Db + De + Dd)2 g

Di = signal from excore detector channel i. Tq shall not exceed 0.03.

3.10-3 Amendment No.' 29, 38,48 0

'O ON

]1 b&

h, a

4.1 If the measured value of Tq)0.03 but <0.10, or j nn excore channel in inoperable, assure that the total radial peaking factor (Ff)is within the provisions of Specification 3.10.8.2 once l

I per shift.

4.2 If the measured value of Tq is > 0.10, opera-l tion may proceed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> as long as Ff is maintained within the provisions of Specification 3.10.B.2.

Subsequent operation l

for the purpose of measurement and to identify the cause of the tilt is allowable provided:

a) The THERMAL POWER level is restricted to (20% of the maximum allowable THERMAL POWER level for the existing Reactor Coolant Ptsop combination, and b) Reduce setpoints in accordance w. ch Specifi-cation 3.10.B.2.2.

l 5.

The incore detector system shall be used to confirm l

power distribution, such that the peaking assisned in the safety analysis is not exceeded, after initial fuel loading and after each fuel reloading, prior to operation of the plant at 50% of rated power.

6.

If the core is operating above 50% of rated power l

with one excore nuclear channel out of service, then the azimuthat power tilt shall be determined once per shift by at least one of the following means:

a) Neutron detectors (at least 2 locations per quadrant).

b) Core exit thermocouples (at least 2 thermo-couples per quadrant).

7.

The pre-trip li,its of Figure 2.1-2 constitute l

Limiting Conditions of Operation.

C.

CEA Drop Times 1.

At operating temperature and 3 pump flow, the requi rement for the maximtsn drop time of each CEA shall be not greater than 2. 7 seconds f rom the time the holding coil is de-energized until the rod reaches 90% of its full insertion.

3.10-4

~D**D f9 9

' )f'f(

}[

Amendment No. 29, 38, 48 j

g o

l i

-p

This sheet purposely left blank a

I Figure Flux Peaking 3.10-2 MAINE YANKEE Augmentation Factors Technical

ecifications 3.10-10 1

,, /

l t"__

3_ r. ___. 4 -

- _--q*-k3f - '

~

_\\.

e C C'

~-

~~'_-* "

~

2=--

-=/:r/d25=rEN_.____

_ L-j _ 4_\\%

j&t~

^\\_

s'

-s___.___

-r--

qp 5=;Y., O

  • .S~/ -

._=, _\\ :.

G

. _. _ _-5_ :i;. ; ;f.=-/,._,

-/

. _- "_ g;-% n-t-

ww

..._...___. _ _.s 3

.,..,-.-gn._

.'-e L= =.. _ _. /'~O

\\~' -h---__T - =

= ;

r n

w=,= s=i a._

a r-'__

.a_---~-r,'

--. N =\\-

g( y, 3e

--~

._4 t

g5 60

._ _.2_

_~

=

. _. _, _ ~

._v

_==

' ' = '

_3_.. _

n u

- - - - = ~=r_ _

!=. -__--=.----;

c

- = n4

?-

l 3

g-.

[=-

_. _ _ _ _ ~ =

[

,., Lq.

g g

=

y itEis El ===_ -.~._--- _

C -- _ = ;_-

-- = ;-_ :.=r.== === === :._. _ _.

.._ := =a _= =

i

  • = = = = = = = - - -

"= *~

40 l

. 5

.4

3
2

.I O

.I

.2

.3 4

.5 l

Syt::::letric Offset =Ag. -L U

3 l

PAINE YANKEE Excore Monitor S.O. Alar::1 Band for LOCA LimitinS Figure

,.echnical C.onditiens of Operation '4 hen Incore Monitors are

-3.10-3 i

Specifications inoperable 3.10-t1 Amendment No. 19, 38, 40, 48 o

Note:

1.

Th.,is curve includes 1C*.* calculational uncertainty Ft.= F'

  • 1.03 2.

R 3.

Measured Q should be au:;nented by measurement uncertainty (37.) before ccmparison to this curve.

--4::.: : - = :==:... 4._=. 4 ::.......:... m i,::- := :=:"=:14. A p.:..:.

3...

1.69

..:.._u...____..

.a...l.......:=p:::t.: =:a a

~t""~

en a:

U E

1i. 6L,,"1 =: p "

m.......... ;:=:.:. --=_:.=;==.= u n...a m n..y =.. /%.= =n6..

1, 6 3 I 68

.ru u

.2

= u

== r. _.. _,. = =u. : : =_n =.. :. =.. _

-?

  • Y -**

-. _. 3 't.......... _.. _..!.:. p.: =. :.:. 2. 1:....:. =. :. u =..n..r: n.. " _ = i. n...,......r:

P

.... :=.

l~..E.

}

p-

_... =... "}.. a..

n

p n:m== q.:..

.- ~

c6n. nl:;- ;- q,ndEil=...terin=...=....F:a---*-----*---3 i =

/.__;:2.= -,-

- e t- ;:n.-.1:

=

2-.

,.. U, 1,. /

:. f.. _. n:r. : =..
r. n.. = t.
12.. :..nu.m_:::: !. =... =.......=.. _... a.
. : : e =...

'r-) 8 ;:.

_._..r:n.._-n...,=_=..=..,,=....m........m.

t..

2 1.66

.. =,1: =,

,,,,,,m..,,+.

.,...,...,.,.1,,-.,,,._,au_;,..=-=n-"/==-_,2,=,2=:,..,,....

t, u

n.

n-in r 2 2: :n : r

. -- --- : : ; -.. -~~

- - - - - i =- n =- ; ::. :n-.= c n-y<.._-. =-. =- - - :.: t : -- '.';....

1.:t: r.:~6. ~b......

= -: n r. :.

2.

- :=:-

"r =:.

u r-

~

' a u~.;:= p=. ".....:.n."x r = ::=.:.ep' ::"=r:; ;..7~

o 1.65 "n =:..u.

n=

.up-.

+

4.w

- EF :=-
1: - m:n

"-m n=::n =

-n

=--

.c n

Hin.;p~.iEi.iji:i"i;i r" "t"-. 195=12r'=il".aa."T:Ep".i iiEij:'".iimi r:i y'

,=__= =f. ' : ". _... =~.=q g=_.r 2 :=_u=_'

--g"

" - ~ " -

1.64 u:=p. ": n rr.c

n:.n=y..=.2 i..,
- n.

-.-..a,...._-..=_..

ur u,m nz:.u r-n..._. :.r..- :.-

. :.=_= =.. _ =. _ t.. =. :_-:2 :. :..........r. _=_.1 : : "

u. a..

.........._.._._.b._...._b._....,..=_: :.

r

,Aag

:_n_ *: =. t..r.r..=_.:. =... a..--.._."..

ao b

-.- - - ~.

1.OJ

=.. n n n.;.. p...=..__ _.i =n.
=_ r.n. n_=..r. _. rn_=.u.._.:.=.. ; =_=_ _:". _ :..

.___: -.2.=_. :. r.. : u. s. u uza._.".".'..___..'_.......u- " ~ " ".; c '- ' "- - * " = = ", ". ' ;

=- : = = : -
n ::=n _=.::. :..:. 4.

y

:::ns.:n;=h:='"="c [==:ju.- -

un:..

=

~

...r_.a. = =: :_" = :r-=_=.n r:

=t s.= re n;.., =. ". i c = :::r": p :. p :

~2 1*62 2

.L.:._.

6

t t m t - r " =_:--.

....___.i... = ann n -.....

ni..n-w

,...1._u..............~ q~ -

i r =.= n= u ;c = :! _ -r= :.

a 1.61

.."b..............'...'...'.

.... ".... "_ _..__ i._._..i.._..... _._..

m=

=:" n

". h. ". k :. ""..._.

"..... l :_. _. -. _. i

..:TM._........."."......a_...._...

.. ". -".....g t,

=

.j :..; l;,.0

.r -

l :~ ;.._:

a;;,,, u -

--- q r-nu ;:: -

-* n !. -_ -

- t t " 1 u j a n j :=-- =* =::_'_* D C 1 *r.-

1.60 0

2 4

6 8

10 12 13 Cycle Average Exposure (KMUT/.Yr) t D W D

, r0 '

dM..

by e

j\\ u u

Allowable Unrodded Radial Peak Versus Cycle Average e.igure MAINE YANKgg Technical Burnup 3.10-4 3

  • 10-l*'

specifications Amendment No. j$,,(9, 48

. -.. ~..... -.....

!!cte :

C"A's are to be m.aintained at or above the 100^

power insertien lini: when appl in; 3.10.3.2.2b l

f

_..... _.... _ =. _... _.... _ -......_..._..___.=x.n_...=__.........u..y==.=.2._;.._:2._.~..

I' 100

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

5.! 5 i.~" 3 5 f 5 3 5 !5 5 Ei M !!*: E_? ~--? @.~- 5 5.~~~~~h.EI U ~ E N~

i M

_D'_f.5'-5!E" "-f 5#" #i."_l #i~ -5E #_~ ! E5.-E-5:5=5555'Ei I

.. - - - _ = _

==.--..;

-_-.._:;=__.__.-.-___.__.___...-.-..u._.__;..=____=_..- -.

_.. _. = - " " * * * *.

3.

4% ",4 =.=- * * *-

-._~=._-=--.._--:.=._:==..=__=__.====--_=========----

Eji2 : ;;; =E:==.

_E==~=_: t.;:__.F-E E= i_-E_ijii=.=. =.E.iE-.=.:;i=-iE ::f

_. _ _....~

~ = -mi%. _ _.. _.=___._=~~~.:=--.E=_======---==.===-~.i=======

.. _ __ --- -W= *?_2.'... -. T. _.-^. ~'-~ E=.__ __ ~-~ : ~~. _.. = =

u 80

__ w,

u 3

_.._._._x..___.__._.._

_,...._g,._..

.m

__ _ _ = = -

~=.g=g_.=...__.__._g.._=2====----=====_.

-x a

---.hm : ; 5 C_-~_'----"

_ -- -==~ - _ _ _

w o 70

__\\_g e p

x n

x E

-- - ---_ _ __ N_ ;- - -- -

^ ' -

60

%4 Q:

,.=%W}-

O

_w

..___._._._'_:n__.

w y ___

50 n.._-

==,,-a - y' +

40

-. - - _. - _ - =

0 2

4 6

8 10 12 14 16 18 20 22 24 T

Increase in F (above figure 3.10-4)

R O

U e

MAIiE YAEEE Allowable Power Level vs. Increase in Unrodded Total Figure Technical Radial Peak 3.10-2 3.10-13 Specifications Amendment No. 38, 40, 48

3.15 REACTIVITY ANOMALIES Applicability:

Applies to potential reactivity anomalies.

Objective:

To require evaluation of reactivity anomalies within the reactor.

Specification:

Following a normalization of the computed boron concentration as a function of burnup, the actual boron concentration of the' reactor coolant shall be periodically compared with the predicted value. If the difference between the observed and predicted steady-state concentrations reaches the equivalent of 1% in reactivity, the Nuclear Regulatory Consnission shall be notified and an evaluation as to the cause of the discrep-ancy shall be made and reported to the Nuciear Regulatory Commission in accordance with Technical Specification 5.9.1.6.

Basis:

To eliminate possible errors in the calculations of the initial reactivity of the core and the reactivity depletion rate, the predicted relation between fuel burnup and the boron concentration, necessary to maintain adequate control

' characteristics, must be adjusted (normalized) to accurately reflect actual core conditions.

b' hen full power is reached initially, and with the CEA groups in the desired positions, the boron concentration is measured and the predicted curve is adjusted to this point. As power operation proceeds, the measured boron concentration is compared with the predicted concentration and the slope of the curve relating burnup and reactivity is compared with that predicted. This process of normalization should be completed af ter about 10% of the total core burnup. Thereafter, actual boron concentration can be compared with prediction and the reactivity status of the core can be continuously evaluated, and its occurrence i

would be thoroughly investigated and evaluated. The methods employed in calculating the reactivity of the core vs.

burnup, and the react burnup, are given in the FSAR.(1)ivity worth of boron vs.

References:

(1) FSAR, Section 3.4.7 1.15-1 I

9 Amendment No.19, 48 w

Retrieved from "https://kanterella.com/w/index.php?title=ML19322E321&oldid=4775040"