ML17329A061
| ML17329A061 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 07/23/1990 |
| From: | AMERICAN ELECTRIC POWER CO., INC. |
| To: | |
| Shared Package | |
| ML17329A060 | List: |
| References | |
| NUDOCS 9106250244 | |
| Download: ML17329A061 (11) | |
Text
RECOMMENDEO TECHNICAL SPECIFICATIONS MARK UPS Attechrent 1 to AEP-90-231 NS-OPLS-OPL-11-90-463 9106250204 900723 PDR ADOCK 05000315 P
PDR Page 12 of 18
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Attachment
'. ta AEP-90-231 HS-OPLS-OPL-1 1.90-463 Page 13 of 18
668 658 00 Ps)'~
UNACCEPTABLE OPERAT ION
~~0 Psa 638 628
~200 Ps jy
~000 Ps) 618 j840 Psp~
5'18 588 ACCEPTABLE OPERATION 578
.2
.3
.4
.5
.6
~ 7
.8
~ 'I 1.
1.1 1.2 POVER I fr ect,ion of noeinel
)
PRESSURE (PSIA)
BREAKPO INTS (FRACTION RATED THERMAL POWER, T-AVG IN DEGREES F) 1840 2000 2100 2250 2400 (0.0, 622.1),
(0.0, 633.8),
(0.0, 640.8),
(0.0, 650.7),
(0.0, 660.1),
(1.13, 587,3),
(1.08, 601.4),
(1.06, 609.8),
(1.02, 621.9),
(0.98, 633.7),
(1.20, 577.5)
(1.20, 586.0)
(1.20, 591.3)
(1.20, 598.9)
(1.20, 606.2)
RATED THERMAL POWER 3413 MWT FIGURE 2.1-1 REACTOR CORE SAFETY LIMITS Page 14 of 18 Attachment I to AEP-90-231 NS-OPLS-OPL-II-90-463
IIEACTOR 'IR lI'YST I H IN'. I ltt)I'llNIAl ION I k II'fTl'0 lNfS cn m O
I ss sD ro szl
~
z>
41 ss
~
II so
<z\\
4J O
>s n
n C)
PC FUNCTIONAL UNlT l.
Power Range, Neutron Flux 3.
Power Range, Neutron Flux, High Positive Rate 4.
Power Range, Neutron Flux, High Negati:ve Rate 5.
Interaediate Range.
Neutron Flux TklI'~L I I'I)INI Not, Ai>pl ical>)r!
low Setpur lit. -
2".S of ltAlL0 1 Ill.ltlIAL I'OWl It llitJlr Set.i>t>irrl IUJX of IIAll0 1IIEINAL I'OWI k 5X of IIAIII) IIIIINAL I'OWI It wr llr a t I>lit! Coils I still s
st!( t>r>sls 5X of IIAII I)
I III l(NAI. I'I)WI It w r t Ir a lime t',orts terr(
~
2
~ t i urrils 25% of BA110 IIIIIWnL ITOWLIt AI.LOWAOiE VALUES Nut. Appl icable low Setpoint -
< 26K of gg)g 1IILRIQL POQER lligh Setpoint -
< llOX of RNED 1IIERNAL POKER S
SS er RATED THER>NL PDREIth a time constant
> 2 seconds 5 ~ 5X of BATED THERNAL POKER with a time constant 2 seconds 30K of RATED THERINL POKER 6.
Source
- Range, Neutron flux l.
Overterrrperature aT 8.
Overpower aT 9.
Pressurizer I'r es u> u--Luw TD.
Pressurizer Pressure--iiigt>
ll.
Pressurizer Mater Level--High P
12.
Loss of Flow IO'tru>>ls l>t r'r!t.urrd See NoLe I
See Note 2
Iujd I>s riJ
< 23t)5 psig 92% of lnstrurrrt.rrt span 90'X of 'design I luw per loop' l.3 x l0 counts per second See Note 3
See Note 4 1865 psig
< 2395 psig
< 93'f Instruaent span
> 89.1X of design flow per loop>>
0,goo
'Design flow is, prrr per loop.
TQLX 3.2-L DNB PgthNETER5 LIMITS 4 Loopl in Operation ac RATED THHNAL POVER Reactor Coolant Syateia Tave PYe55uriz ~ 'r Pree5ure Reactor Coolant System Total Flov Race
< 570.9 F
> 2050 paid 3@i, Coc 6E~g
- ndioated avez'age of ac least three OPH4QLE instruaer.=
loops.
I
.nit not applicable during either a THER~ POKER ra=
cxce5a of 5
eYcenc ra=p increaae in percent RATED THER.'9d.
POWER per otinute o:
a
.HE%Ad. POVKR step inoreaee in exceia of LO percent RATED THERSLL.=:"ER.
- rdicated value.
COOK NUCLEAR PLhÃT UNIT l l
>t4 2-l4 Page 16 of 18 AttaeIrent 1 to AEP-90-231 NS-OPlS-0PL-II-90-<63
i SECL NO 90-280 Customer ference No(s).
P.O.
01538-040-ON Westinghouse Reference No(s).
G.O.
CB 10566 WAF B-07696 WESTINGHOUSE NUCLEAR SAFETY SAFETY EVALUATION CHECK LIST 1.)
NUCLEAR PLANT(S):
Donald C.
Cook Nuclear Plant Unit 1
2 '
SUBJECT (TITLE):
Reduced Minimum Measured Flow 3.)
The written safety evaluation of the revised procedure, design change or modification required by 10CFR50.59 (b) has been prepared to the extent required and is attached.
If a safety evaluation is not required or is incomplete for any reason, explain on Page 2.
Parts A and B of this Safety Evaluation Check List are to be completed only on the basis of the safety evaluation performed.
CHECK LIST -
PART A - 10CFR50.59(a)
(1) 3.1) 3.2) 3.3) 3.4)
Yes X
No A change to the plant as described in the FSAR?
Yes No X
A change to procedures as described in the FSAR?
Yes No X
A test or experiment not described in the FSAR?
Yes X
No A change to the plant technical Specifications?
(See Note on Page 2.)
p p
evaluated in the FSAR be increased?
Will the consequences of an accident previously evaluated in the FSAR be increased?
May the possibility of an accident which is different than any already evaluated in the FSAR be created?
Will the probability of a malfunction of equipment important to safety previously evaluated in the FSAR be increased?
X Will the consequences of a malfunction of equipment important to safety previously
'"evaluated in the FSAR be increased?
X May the possibility of a malfunction of equipment important to safety different than any already evaluated in the FSAR be created?
X Will the margin of safety as described in the bases to any technical specification be reduced?
4.2)
Yes No 4.3)
Yes No 4.4)
Yes No 4.5)
Yes No 4.6)
Yes No 4.7)
Yes No 4)
CHECK LIST -
PART B - 10CFR50.59(a)
(2) (Justification for Part B answers
~
~
must be included on Page 2.)
4.1)
Yes No X
Will the robabilit of an accident reviousl Attech"..ent 1 to AEP-90-231 NS-OPLS-OPL-I 1-90-463 Page 17 of 18
ECL NO.90-280 NOTES:If the answers to any of the above questions are unknown, indicated under 5.)
REMARKS and explain below.
If the answer to any of the above questions in Part A (3.4) or Part B
cannot be answered in the negative, based on written safety evaluation, the change would require an application for license amendment as required by 10CFR50,59(c) and submitted to the NRC pursuant to 10CFR50.90 5.)
REMARKS:
The following summarizes the justification upon the written safety evaluation
( 1) for answers given in Part A (3,4) and Part B of this SECL See Safet Evaluation (l)Reference to document(s) containing written safety evaluation:
FOR FSAR UPDATE Section:
Page(s):
Table(s):
Figure(s):
Reason for/Description of Change:
See Safet Evaluation SAFETY EVALUATION APPROVAL LADDER:
Prepared by (Nuclear Safety):
H.
Behnke 1
Coordinated with Engineer(s):
G.
H. Heberle Coordinating Group Manager(s):
/
Nuclear Safety Group Manager D.
Ru reckt Date:
Date: ~C's.-:
Page 18 of 18 Attachment 1 to AED-90-231 NS-CPLS-CPL-II-90-463