Text

Supplementing Letter of 2/3/1978, Requesting Changes to Sec. 3/4.2 (Power Distribution Limits) of Appendix a Technical Specifications, Attached New Revised Pages
	ML18219D821
Person / Time
Site:	Cook
Issue date:	04/17/1978
From:	Maloney G; Indiana Michigan Power Co, (Formerly Indiana & Michigan Power Co)
To:	Case E; Office of Nuclear Reactor Regulation
References
	Download: ML18219D821 (36)
	v • d • e

Op q/2 i le

~

~L REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS>

DISTRIBUTION FOR INCOMING MATERIAL 50-315 REC:

CASE E G

ORG:

J1ALONEY G P DOCDATE: 04/17/78 NRC IN

8. MI PWR DATE RCVD'4/20/78 DOCTYPE:

LETTER NOTARIZED:

YES COPIES RECEIVED

SUBJECT:

LTR 1

ENCL 1

FORWARDING SUPPLEMENTAL INFO TO APPLICANT"S PREVIOUS SUBMITTED TECH SPEC CHANGE REQUEST DTD 02/03/78'O APPENDIX "A" TFCH SPEC CONCERNING SECTION 3/4. 2 (PWR DISTRIBUTION LIMlTS> PERTAINING TO THE CYCLE 3 RELOAD FUEL TECH SPECS...

NOTARIZED 04li7/78.

PLANT NAME: COOK UNIT 1

REVIEWER INITIAL:

XJM DISTRIBUTOR INITIAL:

DlSTRIBUTION OF THIS MATERIAL IS AS FOLLOWS GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LICENSE.

(DISTRIBUTION CODE A001>

FOR ACTION:

INTERNAL:

EXTERNAL:

B r

-F SCH(i R++W/7 'ENCL G FIL'E~+W/ENC I

HANAUER~~~~W/ENCL EISENHUT~HHJ/ENCL BAER~~~W/ENCL EEB~~~~W/ENCL J.

MCGOUGH4>>W/ENCL LPDR'S ST.

JOSEPH MI

~HFDF i/ENCL TIC+>W/ENCL NS IC~~~~W/ENCL ACRS CAT B4>>W/16 ENCL NRC PDR4HIW/ENCL OELD+~LTR ONLY CHECK~~~W/ENCL SHAO~>>W/ENCL BUTLER+4W/ENCL J

CQLLINS+4~W/ENCL DISTRIBUTION:

LTR 40 FNCL 39 SIZE:

2P+20P THE END CONTROL NBR; 781100045

P. O. BOX 18 BOWLING GREEN STATION NEW YORK, N. Y. 10004 CD April 17, 1978:r r..

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~~CO

~P~+

R~~

R m

CO Donald C.

Cook-Nuclear Plant Unit No.

1 Docket, No. 50-315 DPR No.

58 Mr. Edson G. Case, Acting Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.

20555 (pp prrntf Ifrnnrr~ r.'tr I'IOrty INDIANA ffr MICHIGAN POWER COMPANY rr r

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Dear Mr. Case:

The purpose of this letter is to supplement our letter of February 3,

1978 in which we rec!uested changes to Section 3/4.2 (Power Distribution Limits) of the Donald C.Cook Nuclear Plant Unit No.

1 Appendix "A" Technical Specifications and corresponding Bases.

Since that time we have had telephone conversations and meeting with the NRC Staff wherein these Technical Specifications for the Cycle 3 reload fuel were dis-cussed.

As a result of these discussions we have revised portions of our February 3,

1978 submittal and these new revised pages are attached to this letter.

Justification for these changes is contained in revised portions of the Bases for the above Technical Specifications.

These Technical Specification change rec(uests have been reviewed by both the PNSRC and the required membership of the.

NSDRC, in accordance with the appropriate provisions of our Technical Specifications.

The result of these reviews indicate that these Technical Specification changes will not in any way adversely affect the 'he'alth and safety of the public.

ry truly yours, GPM:em Sworn and Subscribed to before me this ~~ day of April, 1978 in New York County, New York Malone Vice Presid n

Notary Public cc:

(attached) sA 'r Cs'Y NOlwny r ttuLrh, Sl:to of New York No. 4i-4f!06792 Qurriitierf in Ctuccns County Cortificoto filed in New York County'ornnrrssrorr bprres ntorch 30, ]9) ft 781100045

~

J 8

'I 4 'Itl I

l o

C l 8 l ~ l

Mr. Edson G.

Case April 17,1978 cc:

R.

C. Callen G. Charnoff P.

W. Steketee R. J. Vollen R. Walsh D. V. Shaller-Bridgman R.

W. Jurgensen

~

r ATTACHMENT TO LICENSE ANEHDtlENT NO.

FACILITY OPERATING LICENSE DOCKET NO. 50 -315 Replace the following pages of the Appendix "A" Technical Specification with the enclosed pages.

The revised pages are identified by Amendment number and contain vertical lines indicating the area of changes.

Pres 3/4 2-1 3/4 2-2 3/4 2-4 3/4 2-5 3/4 2-6 3/4 2-7 3/4 2-15 3/4'-16

{Replaced by pages 3/4 2-16, 3/4 2-17) 3/4 2-17 {Replaced by page 3/4 2-18) 3/4 2-18 {Replaced by pages 3/4 2-18a and 3/4 2-18b) 3/4 3-39 B 3/4 2-1 B 3/4 2-2 B 3/4 2-5 8 3/4 2-6 B 3/4 3-3

~

0 PUN-f( DlS1Rll]UfJ!)ff Llt'fiS AX!AL FI,UX DEFFEREIICE )AFOg L]Ml11IIG COHDIT10!I FOR Uf'L'IVLT10!l 3.2.1 The indicated AXlAL I'I.UK DIf f'EREHCE (AFD) shall t;. maintained within a

~!4 target band (flux difierence u>>its) aLeut the target flux difference shown on f:igure 3.2-4.

APPL<CI ufLln:

!IODE 1

above 50K!<ATED 'IfIER!I.<L I'OHEf" AL110,'(:

I'ith th

~ indicated AXIAI FLUX I)lFf:ERENCE outsid of 'th.

+5%

target band about the tar(get f1ux difference and>>ith Tf!ERINL PO!fER:

Above 15'f x T(E) of RATED THENIAL I'OWER, within 15 minutes:

1 a)

Either restore,tf;e indicated AFD to within the target band Iitriits, or b)

Peduce ifIERf'"(L PUIIEI< to less than 75'A x T(E)*+ of RATED TllER!li'ii. PO';!ER.

2.

Between 50K ai(d ')5~ x T(E) of RATED TIIERI'AL PO(IER:

a)

PG",ER OPEINT10lf may contin(>e provided:

1)

TI(

indicated AFD has not been outside of the ~54 target band for more than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months penalty deviation cua<ilativ(. dui ing th-pre,ious 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , a",d 2)

(he indicated AFD is within the limits shown on Figure 3:2-1.

Othe>vise, redu-e TIIERIIAL POHER to les than 50X of RATED.l'f!ER!ihL POI.'ER within 30 minutes and reduce the Power Range Neut,ron Flu"-fligh Trip. Setpoints to c 55" of RATED BI.I(IVL PO'i!ER within the next 4 Iiours.

b)

Survoilla>>ce testing of Kf(e Power Range Neutron Flux Charm ls m::y I:e per'foi~a(.d pu; suant to Specification 4.3.1.1.1

!pro; ided the in~ficat d AFD is maintained within th li:uits nf Fi:.u>e 3.2-1.

A total of 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months (i;>oration m:y be ac uAlufated with the Af'0 outs i.le oF the tar get banJ during Lhis testi>>g without penally d viation.

'See Special lest Excel~tin>> 3.10.2

- T(E) is defined on Figure 3.2-3 and pa'ge 3/4 2-15 0.

C.

COO". - UHIT 1

3/I 2-1 Amendment Ho.

0

.P(!l,'ER 0 I STRIBUTIOh LIHITS

~

I.IIlIl'IIIGCONDITION-FOR OPERATION (Continued) c)

Surveillance testing of the APDHS may he perform.od pursuant to Specification 4.3.3.6.1 provided the indicated AFD is maintained with the limits of.

Figure 3.2-1.

A total of. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months of operation may

b. accumulated with th'e AFD outside of the target band during this testing without penalty deviation.

b.

THER'NL POltER shall not be increased above 75$ x T(E) of RATED THEN'IAL POMER unless the indicated AFD is within the

+ 5~

target band and ACTION 2.a) 1), above has b en satisfied.

c.

THER4lL PO'IEGER shall not be increased above SO% of RATED THERHAL POktER unless the indicated AFD has not been outside of the

+

5% target band for more than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months penalty deviation cumulative during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REQUIRl:tlEIITS 4.2.1.1 The indicate'd AXIAL FLUX DIFFERENCE shall be determined to be within its limits du'ring PO'rlER OPERATION above 15~ of RATED THERMAI POMER by:

'a

~

lloni toring the indicated AFD for each OPERABLE excore channel:

1.

At least once p r 7 days when the AFD I'.onitor Alarm is OPERABLE, and 2.

At least once per hour for the first 2~ hours after restoring the AFD Yionitor Alarm to OPERABLE status.

t1oni toi ing and logging the indicated AXIAL FLUX DIFFER""tICE for ea.h OPERABl.E excore channel at least once per hour for the first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and at least once per 30 minutes thereafter, when 'the AXIAL FLUX DIFFEREtlCE Honitor Alarm is inoperable.

The logged values of the indicated AXIAL FLUX DIFFEREtlCE shall be,'ssu~~ed to exist during the interval preceding eacli logging.

D.

C.

COOK - UlIIT 1

3/4 2-2 Amendment tlo.

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'.>>0 '. 0
-.".0..10 0
I 0 20 30 40 60 r.LU;< r~IFr-EnE; cc (')I) %
. Fl':UI'I 3.2 I;<XI&I.F 3 UX All-Itl:BENC>> I.li'.>>ITS AS A I-UNCTIOf'I Ol';'f. I I:9 Tl I n.Inl. I'OIVL'I'I D.
"-. I.V.', - Vt ) I'
.2/'>> 2-4 f'>>'. < ndf,",>>tnt
>>I.10. ~
0 1st
V J
POWER DISTRIBUTION LIMITS HEAT FLUX HOT CHANNEL FACTOR-F Z
LIMITING CONDITION FOR OPERATION 3.2.2.
F~(Z',p) shall be limited by the following relationships.:
IF (E,)3 F0(Z,e)
< ~p
[K(Z)] for P
> 0.5 F~(Z,g,)
< 2 [F~(E
) j tK(Z)] for P
< 0.5 THER/'IAL POWER where P
=
RATED THERii1AL POWER F~(E
) is the exposure dependent F~ limit for zodg L
~,~'s
'"~i"..od in Figure 3.2-3 for Exxo!,'iuclear fuel and in Figure 3.2-4 for Westinghouse fuel and pages 3/4 2-15, 2-16.
E is the maximum pellet exposure in rod/.
K(Z) is the function obtained from Figure 3.2-2 for a given core height location.
F< is defined as the F~(Z,a) with,the smallest margin or the greatest excess of the li'mit.
,".()D!L 1
AC'I I ON:
14iz;h F~ exceeding its limit:
Comply!;1th eiti:er of the following ACTIONS:
1'.>> uce TiiEl'.!iAL POWEP, at least l~ for each 1~
F exceeds th; limit wi thin 15 minutes and simila!.ly reduce the Power Ra.,ge Neutron Flux-High Trip Setpoints within the next 4
ho!.'rs; POWER OPERATIO."i may proceed for up to a total of 72 hou!.s; subsequent POWER OPERATION may proceed p~ ovided t':e Overpower dT Tr ip Setpoints have been reduced at least ll; for eaci!
1>,'
excr.eds the limit.
The Overpower bT 1!ip Setpo-int reduction sha11 be performed with the reactor subcri tical.
2.
Reduce 1HL'f~l:.AL POWER 'as necessary f.o') et ti!e limits of
."i)uci fi(;ation 3.2.6 using ti!'PCHS with the latest ircore r
p and updated R.
Ident! i';.!nri c.n rect ti!e cause of the out of limit condition prior
! o incr~'.asing 1'HEP,'iAL POWER; THER)!AL POWER may then be
! nc! e"..'d provided FO is demonstrated through incore mapping to be within its lime t.
0.
C.
COOK -
UN I T 1
3/4 2-5 Amendment No.
POl'ER 0 I STRI BUTIOfl LlfllTS SURVEILLANCE REQUIRE/'IENTS 4.2.2.1 The provisions of Specification 4
~ 0.4 are not applicable.
4.2.2.2 Fx shall be evaluated to determine i'f F~(2g) is within its 1 imit by: xy a.
b.
C.
Using tI)e movable incore detectors to obtain a power distribu-tion map at any THERt1AL POllER greater than 5", of PATED THER)'AL PQHER.
Increasing the measured F, component of the power distribution map by 3h to account for manufacturing tolerances and further inci easing the value by 5" to accoJnt for measurement uncertainties.
Comparing the F
computed (F
) obtained in b, above to:
~f C
xy xy l.
The F
limits for RATED THERi~1AL POlJER (F
) for the xy xy appropriate measured core planes given in e and f below,
'nd 2
~
The relationship;
'I FxyFx[ 10'(1P)]
where F
is the limit for fractional THERtlAL POl(ER xy RTP oj>eration expressed as a function of F
and P is xy the fraction of RATED THERt1AL POLJER at which F
was xy measured.
d.
Remeasuring F
according to the following schedule:
xy
~
1.
'Hhen Fx is greater than the Fx limit for the appropriate C
RTP xy xy measured core plane but less than the F
relationship, xy additional pcwer distribution maps shall be taken and Fx compared to F
and F
C,
.RTP L
xy xy
')
Either within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after exceeding by 20.",
of'ATED THER) lAL PO';IER or greater, the THERHAL PO'JER at which Fwas last determined, or xy 0.
C.
COOK - VIIIT 1
3/4 2-6
POIIER D I STR I BUT IOII L IHITS SURVE I LLAHCE REQU IREi1EflTS (Con t inued) b)
At least once per 31 EFPD, whichever occurs first.
2. 'lhen the F, is less than or equal to the F
limit for RTP XJ xy the appropriate measured core plane, additional power distribution maps shall be taken and F
compared to FRTP L
Fx and Fx at least once per 31 EFPD.
xy X
J',
The F
limits for RATED xy planes shall be:
1.
Fx
= 1.71 for all RTP "D" control rods or 2.
F< 1.55 for all RTP THERIlAL 'PO';IER within specific core core planes containing either bank any part'length
rods, and unrodded core planes.
f.
The F
limits of e, above, are not applicable in the fol-xy lowing core plane regions as measured in percent of core height from the bottom of the fuel:
Lower core region from 0 to 15",!, inclusive.
Upper core region from 85 to 100ll inclusive.
Grid plane regions at 18.4
+ 2':, 36.6
+ 2"-,
54.7
+ 2." and 72.9
+ 2';!, inclusive.
4.
Core plane regions within + 2" of core height (: 2.88 inches) about the bank demand position of the bank "D"
or part length control rods.
With F
exceeding F
C xy x
J'.
2.
3.
l.
The F~(Z,R) limit shall be reduced at least lX for each
~
1',.',
F exceeds Fx, and 2.
The effects of F
on F~(Z,a) shall be evaluated to determine xy if F (Z,c) is within its limit.
4.2.2.3
'i<hen F~(Z,a) is measured pursuant to specification 4.10.2.2, an overall measured F~(Z,p.) shall be obtained from a power distribution map and increased by 3". to account for manufactur'ng tolerances and further increased by 5:; to account for measurement uncertainty.
D. C.
COOK - UNIT 1
3/4 2-7
POWER DISTRIBUTION LIMITS AXIAL POWER DISTRIBUTIONS LIMITING CONDITION FOR OPERATION 3.2.6 The axial power distribution shall be limited by the following rel at ionshi p:
fF (Z)j 1.95 I K Z
( R.)(PL)(1.03)(1
+ 6 )(1.07)'F L
j p
Where:
a.
F (Z) is the normalized axial power distribution from thimble jurat core elevation Z.
b.
PL is the fraction of RATED THERMAL POWER.
c.
K(Z) is the function obtained from Figure 3.2-2 for a given core height location.
d.
R-, for thimble j, is determined from at least n=6 in-core f)ux maps covering the full configuration of permissible rod patterns above 84/ x T(E) of RATED THERMAL POWER in accordance with:
n R.
= Z R..
n
~
1 ij Where:
FMeas
~i@
T E
LF;,(Z)jMax Rij and its associated crj may be calculated on a full core or a limiting fuel batch basis as defined on page B3/4 3-3 of basis.
e.
F~.
is the limiting total peaking factor in flux map i.
Meas 4'he limiting totalLpeaking factor is that factor with least margin to the F
(E) curve defined in Figure 3.2-3 for Exxon Nuclear 'Company fuel and in Figure 3.2-4 for Westinghouse fuel.
,l T(E) is the ratio of the exposure dependent F
(E) to 1.95 L
and is defined in Figure 3.2-3 for fuel supplied by Exxon Nuclear Company and in Figure 3.2-4 for fuel sup+lied by llestinghouse Electric Corporation.
E is the peak pellet exposure in the limiting fuel rod.
3/". 2-15 Amend...:i.'
POllER DISTRI BUTION LIt1ITS LIMITING CONDITION FOR OPERATION Conti nued f.
[F..(Z)j is the maximum value of the normalized axial distri-bution aIL elevation Z from thimble j in map i which had a limiting total measured peaking factor without uncertainties or densification allowance of FMeas.
oiA o. is the standard deviation associated with thimble j, expressed ap a fraction or percentage of lf., and is derived from n flux maps from the relationship below, or
.02, (2Ã) whichever is greater.
n L
1 Q (R. - R. )2jl/2 nl i 1 j i'
R.
J The factor 1.07 is comprised of 1.02 and 1.05 to account for the axial power distribution instrumentation accuracy and.the measure-ment uncertainty associated with F~ using the movable detector system respectively.
The factor 1.03 is the engineering uncertainty factor.
g.
Fp is an uncertainty factor for Exxon fuel to account, for the.
reduction in the Fg (E) curve due to an accumula'Zion of ex-posure prior to the next flux map.
This correction is only required when T(E) for the limiting fuel segment. is less tha 1.0.
The following Fp factor shall apply:
F
= 1.0 F
= 1.0 + 0.009 x
M p
for T(E)
= 1.0 for T(E)
< 1.0 where M is the number of effective full power weeks (rounded up to the next highest integer) since the last full core flux map.
D.
C.
COOK - UNIT 1
3/4 2-16 Amendment No.
POKIER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION (Continued APPLICABILITY:
MODE 1 above 845 x T(E) of RATED THERMAL POllER'.
g ACTION:
a.
With a Fi(Z) factor exceeding [F.(Z)]S by < 4 percent, reduce THERMAL POWER one percent for every percent by which the F>(Z) factor exceeds its limit within 15 minutes and within the next two hours either reduce the F.(Z) factor to within its limit or reduce THERMAL=POWER to 84% x T(E) or less of RATED THERMAL PO')E'ER.
b.
>lith a F;(Z) factor exceeding
[F>(Z)jq by
> 4 percent, reduce THERMAL POWER TO 84/ x T(E) or less oF RATED THERMAL.POWER within 15 minutes.
k The APDMS may be out of service:
1) when incore maps are being taken as part of the Augmented Startup Test Program or 2) when surveillance for determining power distribution maps is being performed, D.
C.
COOK -'NIT 1
3/4 2-17 Amendment No.
Pn';.".." DIS R18UTI,.'I LIl'iTS SU>V>E I LLAiXCE REOUIREi >EIJTS 4.2.6.1 F.(Z)'hall be Cetermined to be v'ithin its liivit by:
a.
Either using tl:e APDHS to monitor tiie
>,h ">.!>1 s required per Specification 3.3.3.6 at the fol lowiiig I'i <<qt!encies.
l.
At least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , n~d 2.
I u",ediately and at interval: oi'i',
,<,'i, 60. 90, l>i), 240 aiid 480 minutes following:
a)
Increasing the THERHAi POilFIl aibov~
8>lx c T(E) oF
>>>'<1'Ej THERI,NL POHER, or
')
Ilover,.ent of control bai>k "0" i>>ore than ai, accumu'lated, total of 5 steps in aiiy or>> direction,.
b.
Or using the movable incore detectc>>
s at iiie foll~>>ing Fre-quencies when the APDHS is inop>'.i able:
l.
Ar. least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , and 2.
At intervals of 30, 60, 90,
120, 240 and 490 iiiin!iles following:
a)
Inci'easing the THER>~IA!:
PO<>ER ab.ve 8>lg
>l T(E) of RATEO THERvIAL P01'IER>
o!
b) i>ovement of control ba>i>k "0" i>c-:'. tlian all accui>ul>>! ed total of 5 steps in a>); (. e ili>>'",.tion.
4.2.6.2
':,'!>en tt e movabl>e incore detectors ai e u;ed to i>>nnii>>r I,(Z),
.<L Ir'ast 2 thimbles shall be monitored and ai: F.(Z) a>...iii acv e Ii>ivalent lo that obtained
f. cm'the A'DMS shall be mai>il;a~.i< I.
0.
C.
COOK - U>IIT 1
3/4 2-18
'i"<> Ime;it fio,
f
~
I h
2.0 lL-E l
I (20, 1.-I.95) 1.9 A C7 1.8 1.7 L
I
~
IF CE) 2&0 I 0
. F<(C)~
I L L.
I ~
~ h I
~
I
~ *
=:FL
(37);
1. 65' 1
~ 0
~I~
~'r (20, 1;'. 00)
~
I
.9
.8
T-(E-)
ll
~-T(E).:--
h J
i' 181,-. 00)v6
.846 .'
I
-37 hr l~,
t37,.846
.7 0
4 8
12 16 20 24 28 32 36 40 44 48 PEAK PELLET EXPOSURE IN HHD/KG FIGURE 3.2-3 EXPOSURE DEPENDENT FO LIHIT, Fq(E),
AIND NORHALIZED LIHIT T(E)
AS A FUNCTION OF PEAK PELLET BURNUP FOR EXXON NUCLEAR COHPANY FUEL D.
C.
COOK - UNIT 1
3/4 2-18a Amendment No.
A
2.0 IE--
L h
~
~
1. 80 h
~
h IT i-'
1. 70
. 'L
...p
(
1;90 I
I lh
'h 1.0 0.974 I
h I
0.9 h
J W(E 0.8 h
0 4
12 16 20 24 28 32 36 40 44 48 PEAK PELLET EXPOSURE IN HHD/KG
~
FIGURE 3,2-4 Fq LIHIT, Fq(E);
AND NORHALIZED LIMIT T(E)
AS A FUNCTION OF PEAK PELLET BURNUP FOR WESTINGHOUSE FUEL D.
C.
COOK - UNIT 1
3/4 2-18b Amendment No.
IHSTRUNENTATIOH MOVABLE INCORE DETECTORS L It11T I NG COND ITIOfl FOR OP ERAT ION 3.3.3.2 The movable incore detection system shall be OPERABLE with:
a.
At least 75'.l of the detector thimbles, b.
A minimum of 2 detector thimbles per core quadrant, and c.
Sufficient movable detectors,
drive, and readout equipment to map these thimbles.
APPLICABILITY: Hhen the movable incore detection system is used for:
A a.
Recalibration of the axial flux difference detection
system, 1
b.
monitoring the QUADRANT POllER TILT RATIO, or c.
t1easurement, of F
>~ and F~(2,p.)
H ACTION:
Mith the movable incore detection system inoperable, do not use the system for the above applicable monitoring or cal:bration functions.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
K SURYEILLANCE RE UIREflENTS 4..3.3.2 The movable incore detection system shall be demonstrated OPERABLE by normalizing each detector output to be used during its use when required for:
a.
Recalibration of the excore axial flux difference detection
system, or b.
ftonitoring the (QUADRANT POHER TILT RATIO, or c.
t1easurement of F < and F~(2.~)
N D.
C.
COOK-UNIT 1
3/4 3-39
'I
IIASF.S Tire specifical,iorrs of this section provi<le assurance of'uel integ-rity dur ing Corrdition I (ttonral Operation) and 11 (Irrcirterrts of Hoderate frequency) events by:
(a) maintaining t.tre minimum DtSR in tire core 1.30 during normal Gpel'ation and in slrort term trarrsients, arrd (b) 1 imiting tire fission gas release, fuel pellet teralreraturl, a>>d cladding rrr chanical properties to within assurrred design criteria.
In addition, lirrriting ttre peak linear power. density during Conditinrr I events provides assurance that the initial conditions assumed fnr'ire LOCA arralyses ar.e meet and tire ECCS acceptance criter ia limit of 2200"F is rrot exceeded.
The definitions of trot chanriel factors as used in ttrese specifi-cations are as follows:
Ftl aH tleat Flux Hot Charrnel
Factor, is defined as the maximum local heat flux on the surface of a fuel rod at core elevation 2
divided by the aver age frrel l od heat flux, allowirrg for rwn-ufacturing tolerances on fuel pellet.s and rods.
ttuclear Errthalpy Rise Hot Channel
Factor, is defined as ttre ratio of tire integral of linear power along the r.od with the lrighest irrtegr ated power to the aver age rod power.
3/4.2.1 AXIAL FLUX OIFFEREIlCE~AFD)
Target flux difference is determined at, equilibrjum xenon conditions wittr tire par't lengtlr control rods withdrawn fr'orn the core.
The full lengtlr rods may be positioned within the core in accordance with their respective insertion limits and-should be inserted near tlreir normal position for steady state operation at Irigfr power levels, Tire value o f l,he target flux differ erce obtained under these conditions divided by Lhe fraction of RATED THERtlAL PO'I'ER is tl>e target flux <tiffere>>ce at 'PATED TJIEfltlAL POllER lor tire associated cor e bur'rrrrp conditions.
Target flux differences for other TIIERt'IAL PO'.E'ER levels are obtained by mul tiplying the RATI:D 'ittEJttlAL POI~'ER value by the appropriate f ract,ional Till'.RtNL I'0'/lI.R 1evel, The periorlic rrtrrta ting ol'lr>> tar'get.
ftrrx Ltil frr'c'irre valu>> is lu'cr'ssar'y lo I'el lect r'nr'>> IIIII'llllt>I
> l'.Iclr'r.lt.toll',.
0 C.
COOK-Utt IT 1
8 3/0 2-1
PO'HER 0 I STR I BUT IOlI L!IIITS Although it is intended that the pla it will I e nperaied with tlie AXIAL FLUX DIFFERENCE wi,tliin the
+
5'1. tar<)et ba!id ab;~ut tli": target'liix difference, during rapid plant THERI'AL PV'>ER re<iuctioiis, c.)ntrol rod motion will cause, the AFD to deviate outs ide of ilie target balld at rc' duced THERI'~AL PGl~ER levels.
This devfati~n will n)i; aff>>
I. the xeno'E0 (willi) the AFO within the target band) provided the tii'~ (iui atio:i of tlie <Ivv!-
ation is limited.
Accordingly, a
1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months I)enaliy de" iatio>> Iimit cu ~u-lative during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months is p~(vided I'oi oi)erat ion outside of the target band but within the limit~ of I'igure 3.2-1 whi ie at
'/HE)iliAI.
'POKIER levels between 50Ã and 75/ x T(E) of RATEL> 'IIIE!IIIAL PO'IIER.
For THERlIAL PO'IER levels between 15K and 50/ of RA'IED TllFPIIrii. POI,"FR, d via-tions the AFD outside of the target band are le~s si<ii)i'f'ica>>t.
The penalty of 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months actual time reflects I:Iiis reduced
=ig:iificaiice.
Provisions for monitoring the AFD on an automatic basis are der i'-ed from the plant process computer through tlie
~F0 II',ii i ter Alarm, The computer determines the one minute average of <.a<'>>f th. <iPEIIABLE excore detector outputs ard provides an ~lari)) i::cskin<le i<):!:..(Iiate!y it'li..
AFO for at least 2 of 4 or 2 of 3 OPERABi E e:<coi.e
. I)a<<n 1: ire outsi '..
th target band and the THERIIAL POllER is (!reat i'lian 7'."L'.
< T(E) oI PATED THERlIAL P'I'PER.
During operation at
'.HE..".iill. I'I)'~>LR 1<.v...ls betwe~
~
50','nd 75'.
x T(E) and between 15;; and 59,': RAlED III'-Pf'v')L I)!)'<IEB, the computer outputs a>> alarm message when tiie pen'~1 ty devial:I!)n accumulate.
beyond the limits of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , respecti'"'Iy.
he upper bound limit (64"'.T(") of RATE!! 'I!II:RIIAI POI;I:R} on AXIAL FLUX DIFFERENCE assures that the Fq(Z,a} envelope of 2.32 times K(Z) x T(E) is not to exceed during either normal operation or'n the event of xenon r.distribution following p;>>e" cli)n(;<!s, Tl e lo ~:-:;
bound limit (50Ã of RATED THERIACAL POIIEP) is based oii tlute <1::t tliat THEPl~AL POWER levels below 50/ of RATED II<ERIIAL I>>"";R, tl.e <<verage linear. nea. generation rate is half of il;s ro;;:ii,'l nl.eieti-.<j va!ue.
and below.ha't value, perturbations in lo a'. iz'J f iu.-. <Il~ii ibuiiors cannot affect the results of ECCS or ONBR anilyses iii a 4 i;iei which would adversely affect the health and saity oi i!i')nbIi~.
Fijju) e B 3/4 2-1 sliows a t)'pical ra~ 'lliv
<<>'nut l~>>:
i i<<)r il!e beg iiltlillgof col e 1 iie.
O.
C.
COOK-UIIIT 1
8 3/4 2-2
'.a'.~n<lr"= <t No,
.c
~
s POWER DISTRIBUTION LIMITS BASES a 0 b.
C.
abnormal perturbations in )he radial. power shape, such as from rod misalignment effect F
l more directly than FR although rod movement has a direct influence upon limiting Fg to wtthin its limit, such control is not readily available to l>mit F H'nd errors in prediction for control power shape detected during startup physics tests can be compensated for in F
by rystri-ting axial flux distributions.
This compensation for F~
is less, readily available.
zH A burnup dependent, F< is specified as a result of the ECCS evaluation'n accordance with 10 CFg Part 5G Appendix K and to meet the acceptance criteria of 10 CFg 50,46, The basis for this dependence is given'n document XN-,26-51, Supplement 1,
2.
and 3 ~
3/4.2.4 UADRANT POWER TILT RATIO r
The quadrant power tilt ratio limit assures that the. radial power distribution satisfies the design values used in the power capability analysis.
Radial power distribution measurements are made during startup testing and periodically during power operation.'he limit of 1.02 at which corrective action is required provides DNB and linear heat generation rate protection with x-y plane power tilts.
A.
limiting tilt of 1.025 can be tolerated before the margin for uncertainty
.'n F
is depleted.
The limit of 1.02 was selected to provide an allowance for the uncertainty associated with the indicated power tilt.
Th= two hour time allowance for operation with a tilt condition greater, than 1.02 but less than 1.09 is provided to allow identification and cor-rection of a dropped or misaligned rod.
In the event such action does not correct. the tilt, the margin for uncertainty on F.is reinstated by
'educing the power by 3 percent for each percent 3f tilt in excess of 1.0.
D. C.
COOK-UNIT 1 8 3/4 2-5 Amendment No.
~ i Ob "l'. DISTRIBUT!Ol! LI!<ITS SES 3/4.2.5 D'!B PARA!'ETERS The limits on the DHB related parame<~rs ass.)re that e).-h of the parameters are maintained v!ithin the )!or)).>> sl.ea(!" 'la! e
<.))":;1)o! e of ope! ation assufl!ed in thu', t! ansient and ac:.<dc "l. a'!;ilyce<>>.
!hc 1i!)<!ts>>e consio+ent with the initial FSAR assumpti
~l"s
<!nd
!<a.. (
be<an.'al) "ic<<1'.i demonstrated. adequate to maintain a mini)))>>'<!.'l'!:I? ).l 1."('.,)>>o))))!:o<.:)
f..: li analyzed transient.
The 12 hcur periodic surveillance of ).nes" pa! a)!<ete) s t!!r.i i<)-
strument readout is sufficient to ensure t>>at.
l.ho !)ara;)e);e) s a! e rest(!! <<!l within their limits following load change."
an<I ot!!e). e,",poet)<!
t<.ansi~<)<.
operation.
The 18 month periodic measure<<;tnt, o," t.'.
i)CS '.otal flow )ate is adequate to detect flow degradation and ensure co< relation of ti!e i"liiw
))dication channels with measured flow su"i !:hat tl!e il<dicat('d percn>>t flow.will provide sufficient verification 'f l'lo"l
< ate-nn a
12 l)<<<Jr ba
<s.
. f 4.2. 6 AXIAL PO'<!ER DI STRI BL)TIO<<
The 1imi t on axial power distributio) e!!s))< e"
)'i)~ t'
. "<1 l Le controlled ano monitored on a more exact !i~sis tn) (<ug), ))o!j (,! tl)e Af'l',.')h<en operating above 84;.: x T(E) of RATED !FlEPi'<'l.. !'))'<'..
!'h!. <i(i]iti<i<:i) limitation on F
is necessary in order to l>rn')de assu) an<'0 tllat pe:!!:
clad temperaturq<.s will remain below the EC! S <icce!:!."nce cri terl<l li)))iI of 2200'F in the, event of a LOCA.
The unit may operate with fuel assemblies supp)ied by the Exxon Nuclear Company and by liestinghouse Electric Corporation.
An F. linit has been specified for each of these tso fuel types.,
The has s
for the limit speoifj;cation Figure 3.2-.4 is provided in Reference 6.
D.
C.
COOK-U!!IT 1
03/4, 6
< f'" <<" 'Ql<t ig'..
C
XNSTRUMENTATION BASES 3/4.3.3.6'AXIAL POWER DISTRXBUTXON MONXTORXNG SYSTEM (APDMS)
The OPERABXLITY of the APDMS ensures that sufficient. capa-bility is available for the measurement of the neutron flux spatial distribution within the reactor core.
This capability is required to 1) monitor the core f3,ux patterns that are repre-sentative of the power peaking factor in the limiting fuel rod.
The limiting fuel rod is the fuel rod that has the least margin to the exposure dependent Fglimit curve, and
2) limit the core average axial power profile such that the total power peaking factor F in the limiting fuel rod is maintained within accept-able limkts.
R factors are used'o determine the APDMS setpoint limits (F (Z))s.
On a full core basis the R.
and c> factors are cal-culated in accordance with the equations on Pages 3/4 2-15 and 3/4 2-16.
However near BOC, thimbles not in the region of fuel which contains the limiting total peaking factor, Fgil, may not follow the axial power distribution of the hot, rod.
This situation will manifest itself in the form of large crj for thimbles not in the same region as the total peak F
Xn this situation, if the rod with the limiting total peaRing factor were to move from one fuel region to another, the neutron flux in the thimble with the smallest crj would not necessarily follow the axial power dis-tribution of the power in the new limiting rod.
In order to cope with this difficulty,.it is permissible to calculate as many 'b"'s and F 's for each thimble as there are fuel 3
j'ypes or regions in the'ore.
Each K
and a> for a thimble j is to be calculated from the equations on Pages 3/4 2-15 and. 3/4 2-16 with the following exception.
For each K and cr for thimble jf a different Fgil and T'(E) shall be used.
The different o~'s and Rjzs for thimble j shall be calculated substituting for F<.1 and T(E) the values pertaining to the limiting peak relative power from each fuel region.
Obviously for one of these calculations the limiting Peal: relative power fro~ one region will be he core limiting total peaking factor.
If this option is chosen, the o-. set to use for APDMS thimble selection and the RE set to use for Rhe calculation of (FJ(Z)
)s shall be the set obRained using the limiting peak relative power from the same fuel type as the F.1 from the most recent incore Qil flux map.
D.C.Cook -Unit 1 B 3/4 3-3 Amendment No.
C ATTACAltENT
~
REFERENCES Exxon Nuclear Document XH-76-51, "Donald C.
Cook Unit 1
LOCA Analysis Using WREN-Based PWR ECCS Evaluation Nodel (ENC WREN-II)," October, 1976.
2.
Exxon Nuclear Document XN-76-51, Supplement 1, "Flow Blockage and Exposure Sensitivity Study for D.
C.
Cook Unit 1 Reload Fuel Using ENC WREN-II Nodel," January, 1977.
3.
Exxon Nuclear Document XN-NP-76-51 (P) Supplement 2 "Flow Blockage and Exposure Sensitivity Study for 0.
C.
Cook Unit 1
Reload Using ENC WREN-II Nodel," January, 1978.
4.
Revision 1 to Safety Evaluation Report on the:Exxon Nuclear Company WREN-Based Generic PWR-ECCS Evaluation Hodel Update ENC-WREN-II for Conformance to Requirements of Appendix K
to CFR 50 by the Office of Nuclear Reactor Regulation, January 5,
1977.
I 5.
Exxon Nuclear Document XH-NP-76-51 Supplement 3 "Flow Blockage and Exposure Sensitivity Study for D.
C.
Cook Unit 1 Reload Using ENC WREN-II Nodel," Narch, 1978.
6.
G.
P. Maloney letter (Indiana R Michigan Power Company) to EDson G. Case, (NRC), dateD April 6, 1978.
T',~
'l I'

ML18219D821

Text

SUBJECT:

Dear Mr. Case:

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