ML19256A609
| ML19256A609 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 12/15/1978 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19256A606 | List: |
| References | |
| NUDOCS 7901090089 | |
| Download: ML19256A609 (30) | |
Text
-
J
,p* * * %,,%
UNITED STATES j
j' ' '
NUCLEAR REGULATORY COMMISslON
,~)
j WASHINGTON. D. C. 20555 SACRAFENTO MUNICIPAL UTILITY DISTRICT DOCKET NO. 50-312 RANCFO SECO NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Arrendment No. 26 License No. DPR-54 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amencment by Sacramento Municical Utility District (the licensee) dated Septemcer 13, 1973, as sucolemented November 15, 1978, camelies with the standards anc recuire ents of the Atcmic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; 8.
The facility will operate in confomity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (11) that such activities will be conducted in compliance with the Comission's regulations; 0.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amencment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
790109cmsq
6
. 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. OPR-54 is hereby amended to read as follows:
(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 25, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATC'.Y CCMMISSICN fp '%dd ).,k - hMl "
)
C j
V Robert W. Reid, Chf'ef *
'l Operating Reactors Branch #4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: Decemeer 15, 1978
ATTAC!41E*li TO L! CENSE APE.1CMENT NO.26 FACILITY CPERATING LICENSE NO. 3PR-5a CCKET NO. 50-312 Revise Appendix A as folicws:
Remove caces Insert oaaes vii vii viti 1-3 1-3 l-4 1-4 2.1-1 2.1-1 2.1-2 2.1-2 2.1-3 2.1-3 Figure 2,1-2 Figure 2.1-2 Figure 2.1-3 Figure 2.1-3 Figure 2.3-2 Figure 2.3-2 3-32 3-32 3-323 3-33 3-33 3-33a 3-333 3-33b 3-32b Figures 3.5.2 3.5.2-7 Figures 3.5.2 3.5.2-12 Changes on the revised pages are shown by marginal lines. Page 1-3 is uncnanged and is provided for your convenience only.
RAf(C:iO SECO UNIT 1 TECHi;iCAL SPECIFICATIONS LIST OF FIGURES TLvice 2.1-1 Core Protection Safety Limit, Pressure vs. Te=perature 2.1-2 Core Protection Safety Limi:s, Reac:or ?ower Imbalance 2.1-3 Core Protection Safety Bases 2.3-1 Protective System Maximum Allowable Set ?oints, Pressure vs.
Temperature 2.3-2 Protective System Maximus Allowable Set Points. Reactor Power Imbalance 3.1.2-1 Reactor Coolant System Pressure-Te=perature Limits for Heatup for the First 5 EF?Y 3.1.2-2 Reactor Coolant System Pressure-Temperature Limits for Cooldown for the First 5 EF?Y 3.1. 2-3 Inservice Leak and Hydrostatic Test (3 EF?Y) Hestup and Cool-down 3.1. 9-1 Limiting Pressure vs. Te=perature for Control Rod Drive Operation 3.3.2-l Rod Index vs. Power Level for Four-Fu=p Cperation, O to 160 EF?D 3.5.2-2 Rod Index vs. Power Level for Four-? ump Cperation, 140 :o 290 EF?D 3.3.2-3 Rod Inden vs. Power Level for Four-? ump Cperation, 270 to 310 EF?D
- 3. 5. 2-.
Rod Index vs. ?over Level for Three-?u=p Operation, 0 to 160 EF?D 3.5.2-5 Rod Index vs. Power Level for Three.?umo Cperation, 140 :o 290 EF?D 3.3.2-0 Rod Index vs. Power Level for hree-?u=p Cpers:1on, 270 :o 310 IF?D 3.3.2-7 A?SR Withdrawal vs. Power *.evel, O to 160 IF?D 3.5.2-3 A?SR Wi:hdrawal vs. Power Level, 1;0 :o 290 EFoD A=end:ent No. 26
.*11
e' s
LIST OF TICL*RES (Cont'd)
Figures 3.3.2-9 Core Inoalance vs. ?cwer Level, O to 160 IF?D 3.3.2-10 Core Imbalance vs. Power Level. 140 to 160 EF?D 3.3.2-11 Core I=oalance vs. Power Lavel, 270 to 310 EF?D 3.3.2-12 LCCA Limited Maximum A11ovaole Linear Heat Race 3.3.4-1 Incore Instrumentation Soecification Axial Imoalance Indication 3.3.e-2 Incore Instrumentation Specification Radial Flux Tilt Indication 3.3.a-3 Incore Instrumentation Specification 6.2-1 Plant Organi:stion Char:
Rancho Seco Unit 1 Amendment ';o. 26 viii
R x* *.' C'd. O.c "M. v 'v' *.. l T i c
TECHW CA1. SPECIF CAT'ONS
.n..a
, r
,,,t,..
4.n o.a..,.-...
eu
.4 A protecticn :na n n e l. as shcwn in :.gure 7.1-1 :: :nu
?-'..
n.
s-
- ar e
'r
.v,
.o,e:+
- a i nse-r;
- >
ne ::. :. ]ur 'n:eoenaen: :nanna.;..
t
.,.e.>.
a_..n. is.... ano s.2 2.
t.
u.....o,,,.i.2
- w...,.
.a i
- o.....
2 a. <... p 2,. 2......,-).
....b
,2..
n
...u--.
s.
. +.
..w.
.. 1 a.......:..,
..e o...,. 4.,
.4 i
4.3..a.
J u.,,m.. a 2. 2. c_-
3
-r
,... a o,.
........2.
w..a.n e.t 4n
.s
..]
.w
.u..,.., c e. 2
.. g byptss s% itch and a snutd:.n bypa s s 3%;;:n.
1.4.4 Reactor Pro:ectier. Systen. :i:
This syste ; ill:es resc:or : rip modula relars. c c i '. - - o.
cant c 3) in all four of :he pro:ec: ion :hannels as sacun in :igure 7.1-1 :.' :Lc T.'.. :a provide reac:or : rip signals for de-ener;;;ing :ne ;;x ca ::rol res. r i-z e
...... o. =. a k c - s.
. %,. e o n. a 1. o d.'. '. ~. a...'.o..a.ase s
...>-..2..,a.d.
4.'".'.".u>
a a one-ou t-o f-clo-times-:vo icgic.
Iaca element o: :. a o ca-c u t-e.- : ac - :ine s -
- wo lasic is con:rol'ed by a separs:e :vo-aut-of-: cur '. e ; i c :: : : e :a.
reac:or protec:ian enannels. iiith one channci Sveas:ec and ; :r t t. vd :ne
- vo-ou :-o f-f au r,.cg.c :anc::ans as a :vc-ou:-e:-:nree.
t a c
- c..
- 'ree 4
. c 3. :
ac:ive channels.
4.3 Sa:.ety :eatures System.og.,:
This systen utili:es relay contac: ou:pu: from individaal channels arranged in
- hree analog sub-sys:e=s and tuo vo-cut-af-:nree lag; sub-sys:eco as snown 3 e,
- ,. 2..
- m..,. e r o, g 4.
a.... s v. 2. a --
.43
.. :., u.
s.
..22 1
- 4., g 4,,....
...5 s.e
-'5 "..d a...
a a.' '..", 'e.'..--a.se."..'.'.'...-.
.' t.
s ' 3. 1 ' s.'.'
two-o:- hree basis :."e 2-.'a...'..'.
p.'s e or an.'
given parameter.
1.a.6 Oegree of Redundancy a..J-.
. ". =... u..'. e..'
y' e.ab.'e.."..-.. C. 2
't 5. e '.'.' a. - = a.c e b e.~. e e..... e..u
.". e. 3.'
d.
channels vnich, vnen : ripped, will cause an auto =a:i: system :r.p.
t.
- n., 3. p., e....g..., e
.......,e..g..
.i. s..,
. 4.o.es..
e.,e.en..
n a p...en..<,n
-ha...e.,.o,.,,..i,....
<s a.es. o.e t o,.4.-
A. <p.es.
associated trip action.
-s 3.5.3 c.
..e
.es.
....,...u...
S.
a..,,. a.-....
.2,
.hd 4..,40r...,n
.,.e a,. <.. e a.-
A
.w,...a.n e
.es.4.a
..s. s.
..w v.
,.,pe,.,a-rc n. s e, '.. c.'...'., a '..-. 1 n c, c.... g '...'..... -
.u.e
..,.an e. c..e < s.,
4.-
r..
4 g
aw-.4.,.,
. w... e a,,,..,...
1.5.3 'nstrumen
hannel Check
~.e.'..='.2.'..'e
. a c.. p r. J..>
.'..S-.".....'..~..*.:.-..-
.\\n '.~.. s. ~ ~ e.... a.. e i
.-."..'.s
.s a
44.
a.<.,
......e
. e.,.a. 4..,. 4.. 4, v,. a3
. u. s. a.
a n.
e s. y C. S e../ a t..,..-.:
4...a s...
..s..
4 Oceparisen a:. cu:pu: and,,or s:a:e a:. incepencen: :nannels reasur,.ng :n* same variable.
1-3
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATICNS Ce:.u.-
.i. ).. - -
ynstru=en u na nne,..2..:ra::an An instrumen: nannel calibration is 2 tes:. 2nd 22.'us:ren:
- ::essar>
establisn :na: the enannel cutpu: respen:s. :h 2e.c;:2:.e r_ni. an; ac.
to knctm values of :ne para e:er '..n:ca : a :nannel
=2sures er m.
a c ; 2. 2.
s;=ulation of :nese values.
Ca'; bra::cn anal. enes-ca.2 :ne
- .re :.-
including equipnent ac:aation, alars, or trip anc saal. ce re_.....
.ac.
the channel :est.
1.5.5 Heat Salanca Check A heat balance check is a comparison of the indicatec neutron geser and.:te ener=al power.
1.5.6 neat 341ance' Calibration An adjus::en: f :he pcuer range channel amplifiers -utpu: :, agree ei:n core thermal power as determined by a hea; balance consideria4 a.1 aea: '. c a, _
and additions.
1.6 QUADRA:C ?CWER !!LI Quadrant to average power til: is expressed in percen: as defined oy :ne following equation:
Power in anv core cuadran 100
-1 Average for all quadran:s 1.6.1 Reactor Power Imbalance Reactor power imbalance is the power in :he :ap half of :he core =inus :he power in the bot:om half of the core.
1.7 C0!CA WE!C !!CECRIN Containment integrity exists when the following condi: ions are satisfied:
A.
The equipment hatch is closed and sealed and both doors of the personnel hatch and emergency hatch are closed and scaled excep: as in 3 below.
3.
At least one door on each of the personnel ha:ch and emergencv nair is closed and sealed during refueling opera: ions or personnel passage through :hese hacenes.
C.
All non-auta=a:ic centainment isolation valves ard blinc flanges sr4 closed as required.
A=endment No. 26 i-n,
RidCno SECO L* NIT 1 TECHNICAL SPECIFICATICNS Safety Limits and Limiting Safety System Settings 2.
SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1 SAFETY LIMITS. REACTOR CORE Acolicability Applies to reac:ce thet mal pcwer, reac ce =cwer incalance, reactor cociant system pressure, coolant temperature, and coolant f!cw during power operation of the plant.
Objective To maintain the integrity of the fuel cladding.
Soec i f i ca t icn 2.1.1 The comoination of the reactor system pressure and ccolant temperature shall not exceed the safety limit as definec by the locus of :oints establisned in Figure 2.1-l.
I f tne actual pressure /temoerature point is within the restricted region the safety limit is exceeded.
2.1.2 The ccmbination of reactor enermal power and reac:cr pcwer imoalance (power in the tco nalf of the core cinus :ne power in the bottom nal f of the core e oressed as a percentage of the rated power) snall not exceed :ne safety limit as cefined av :ne locus of points (solid line) for the specified flow set forth in Figure 2.1-2.
If the actual-reactor-therma l-:cwer/ reac:cr-:cwer-imca lance :oi n t is acove the line for the specified ficw, the safety limit is exceeded.
Bases The safety limi ts presented have ceen gener3ted using SAW-2 cri tical heat flux (CHF; correlation l') and :ne actual measured flow rate!2).
This develgement is discussed in :ne Rancnc Seco Uni: 1, Cycle 2 Reicad Re= ort, reference tI.
The flow rate utili:ec is 104.3 ercent of the design flow (369600 gpm) based en four pump operation.
(2.3)
To maintain the integrity of the fuel clacding and to prevent fission product release, it is necessary to crevent everneating of the cladding under normal operating concitions. This is acccmelisnec Oy coerating within the nucleate boiling regicn of neat :ransfer. wnerein :Ne heat ransfer coefficient is large enougn sc :nat :ne clad surface ter: era:ure is only slightly greater than :ne ceciant :e-oerature. The accer Ocuncarv of :ne nucleate :ciling region i s ter ec ":e:arture f rom nucleate : oiling" (DNB),
At this point, there is a sha r: reouction of :ne heat :ransfer coefficient, wnich wculd resul in nign cl adding ter: era:ures and :ne :ossi ili:y of claccing failure.
AI:ncugn ONS is not an Ocservaole :arameter curing reac:ce oceration, the coservaole parameters of neutron pcwer, reac:cr coolant " low, temperature, and pressure A=end=en: No.
26 2 1~1
RANCHO SECO UNIT I TECHNICAL SPECI.:lCATIONS Safety Limits and Limi ting Safety Sys:em Se::ings can be related to ONB :hrough the use of the BAW-2 :Orrelatien (1),
The 3AW-2 correlation nas teen deveic ec to crecict NS and the location of CNB for axially unifor" arc ncn unir:rm acat f!ax dis:ri ut icns.
The Iccal CNG ratio (CNBR), :e tinec as tre ratio of :ne neat flux tna: would cause CNB at a particular core Icca:icn to the actual neat flux, is indicative of the margin to CNB.
The minimun value of tne CNBR, curing s teacy-s tate cceratien, normal coeraticnal transients, anc anticipated transients is limited to 1.30.
A CNBR of !.30 correscencs to a 95 :ercent procacili ty at a 95 percent confidence level that CNB will net cccur: tnis is considered a conservative margin :0 DNB for all c=erating c:ndi ticns. The di f ference be tween the ac:ua l core outlet pressure and the indicated reac:or coolant sys:em pressure has :een considered in determining tre core protec: ion safe:y limits. The di f ference in these :.so p res s ures i s ncmi na l ly 43 as i, however, on l y a 30 ps i drco was as s ume d in reducing :ne pressure trio set;oints to correscend to the elevated locaticn wnere the cressure is ac:ually measured.
The curve cresented in Figure 2.1-1 recresents the c:nci:icns at which a minimum ONBR of 1.30 is precicted for the maximum pcssible thermal Ocwer (112 percen t)..nen four reactor coolan t pumns are operating (minimum reac:cr f
coolant ficw is 104.9 cercent of 369,600 gpm).
This curve is based en tne combination of nuclear ower aeaking fac: ors, wi th potential ef fects of fuel densi ficatien and red bewing, wnich result in a more conservative DNBR than any other snace :nat exists during normal coeraticn.
The curves of Figure 2.1-2 are cased en :ne mo re res t r i c t i ve o f two :he rma l limits and incluce :ne effects of potential fuel censification and red bewing:
1.
The 1.30 ONBR limi: precuced by :he combina tion of :he radial eak, axial peak and pesi:icn of :r.e axial peak that yields no less than a 1.30 DNBR.
2.
The ccmbination of radial and axial peak tha: causes central fuel mel ting at the hot soot.
The limit i s 20. 4 <4/ f t.
Pcwer peaking is not a ci rec:!y coservable quanti ty and therefore limits nave been establisned On :ne bases of the reactor power imbalance produced by the powe r pea <i ng.
The soeci fied flov rates for Curves 1, 2, and 3 of Figure 2.1-2 correspond to the ex=ec:ed minimum ficw rates with fcur pumos, tnree pumos, and one pumo in eacn leco res ec:ively.
The :urve of rigure 2.1-1 i s the mos t res trictive of all pcssible reactor ecolant :umo -axi mum :ne rma l pcwer comoinatiens snown in Figure 2.1-3 The :ner al ocwer for :nree-coro coera cien is 35.6 :ercen t due :o a cover fevei i 1.05 = 73.1 l
trip precucea
=v :ne f l ux-f l ow ra tio 74.4 percen t design flew x percent Ocwer alus :ne maxinun ca libration anc ins trument error. The maximum the rma l acuer for Otner ::cian: cu.mo concitiens is precuced in a similar manner. The ac:aci flow wi l l ce:e rmi ne the maximum :ria seccoint for :ne f l ux-i f l ux-f i cw :ria as actual f l ov times 1.05 Amencmen: ::o. 26
RANCHO SECO UNIT I TECHNICAL SPECIFICATIONS Safety Limits and.imi:ing Sa fety System Set t ings The curves of figure 2. f-3 represent :Me conditions at wnich a minimum CNSR of 1.3 is predicted at :ne aximum ;ossiale ther-al Ocwer for :ne 3ssumed design flow, or tre local quality at :ne :oint of mi,icum ;NBR is ecual to 15 percent, anicnever condition is more restrictive.
For Figure 2.;-3, a pressure-te oerature point above and to the lef t of the curve nould result in a ON8R grea ter than 1.30.
The 1.30 CN8R curve for four-pump operation is more res:rictive :han any other reactor coolant umo situatien because any pressure / temperature ;cint acove and to the lef t of the four pump curve will be acove and :o :he lef of :ne other curves.
References (1)
Correlation of Critical Heat Flux in a Bundle Coolec by Pressurizeo Wa:er, 3AW-10000, March, 1970.
(2)
Rancno Seco Unit 1, Cycle 2 Reicac Report SAW.
(3)
Rancho Seco Unit I, Cycle 3 Relcad Report SAw-1499, Septemeer, 1979.
A=er.dmen: No. 0 2.1-3
Figure 2.1-2.
Core Protection S4f ety '..mits.
Reactor Pcsar * :414nce inersal Pseer '.tvel.
-- IIS f+35.112)
Curve !
-- ':J ACC EP T A!'. E
( *$0.105)
FO'J R J'J'8
_ ggg CPERAll:N
( 40.30)
-- 90 ria q)
(*35.34 5)
( 32.34 Si r Curve 2
.. gg ACCEPTABLE
( +50 7 7 5 )
THREE AN3 FCUR -
70 PUWP QPERATICN
( 40.62 S)
'97
'~
' II 'I
( 32.57 4)
Curve 3
.. 50
(+50.50 4)
ACCEPT 1!LE TWC THREE. AN F O'J R -
'O
~~
PUMP PERATION 4 50.35 4) 30
-- 20
_. 10 9
e 40 40 20 0
20 40 50 Reactor Power I catancs. 1 CURVE REACTOR l00LANT SE lGN FLOW. ;pm I
387600 2
288374 3
187986 k:end:ent Io. 26
FIGURE 2.1-3 Core Protective Safety 3ases 2400 f 2200-2 3
a c
$:a I 2000--
t:
a e
8 1800-
/
1600 l
l l
560 580 600 620 640 o
Reactor Outlet Temeerature, F Pumps operating Curve Reactor coolant flew. com Power.*
(: vee of limit) 1 387600 112 Four (DNBR Limi c) 2 288374 87 Three (CNBR Limi t) 3 187986 59 one in each teco (quali ty limi t)
Amend ent No. 26
Tigure :.3-2.
PRCTICT'"E SYSTD! :9.7.!'11.? ALLS-A3LI SIT?n:::TS.
RE. ACTO R ?' NE.9
- !F a*.'d CE.
. introu 7:ee r ',e.e s 4 1*2
-- II3
( 25 135 i s-25 lT# I t.22.105s Carve i
- ::i l
acus aitt l rots. w l
[
e l
.. 33 :rturie. I l
I
( 40.40)
I
< -22. i i.
25 ti
l Curve 2 lN,,3; 73,,
actIPratLF g
ha(I ano l l
l sa.s-es.,
l
__ Sa m.ar,,
( 40.53.1) l
,.3 9,
,,,,) 3,
( 22.53.1'
~~
I C u r'.' e ;
a lK t 20.45 !)
aCCIPfasLF
== 40 ?ug *uett l
an0 Nkm 3rfla riCm l
~~
( 40.23 5) l l
23 l
[
L
~
v
~
a I
_. is l~n
~
s a
40 40 20 3
- 3 40 53 Poser i=oalancs. $
CAVE OE51Gil PEACTOR COOLA.'tT Ft.0W, ;;rs t
387600 t
238374 3
187986 Amendment :To. 25
RANCHO SEC3 LMIT 1 TECHNICAL 3PECIFICATICNS Limi ting Ccndi tions for 0;e rat icn F.
I f a cen trol rec in the regulating er axial Ocwer sna;:ng greucs is declared inceeracle :er Sceci ficatien
.'.l.2, coeration above 602 o f ra tec =cwe r may con ti nue a rovi ded :ne recs in :ne group are ;csitienec such :nat :ne roc :,a: was ceclarec inoperable is maintained witnin allcwaole grouc average ocsition limi ts of Speci fication h.7.1.2 and :ne ai:ndrawa l limits of Speci ficat ion 3.5.2.5.c.
3.5.2.3 The wor:h of a single inser:ed :entrol red snali not exceed 0.65 percent ik/k oc rated power or 1.0 :ercent ;k/k at hot :e rn =cwe r except for :nysics :esting wnen tne requi remen t o f Speci ficat ion 3.1.3 shall apply.
3.5.2.4 quandrant Pcwer Til:
A.
With the Quadrant Pcwer Tilt determined to exceed L.920 but less than or equal to !!.07% except for ;nys ics tests.
1.
Within 2 nours:
a) Either reduce the quadrant gewe r t i l t to 1, 4.92%, or
'o ) Reduce ther=al power so aa no to exceed the rmal power, including power level cutof f, allowable for :he reac:or coolant pu=p combination, less ac least 2% for each 1*,
or fraction thereof, of auadrant power tilt in excess of l
4.92%.
Within a hours, take at: ion to reduce the high i
flux trip and flux-aflux-flow trip setpoints at least 2% fou each 1",
or fraction thereof, of cuadrant power :11: in excess of 4.925.
2.
Veri fy that the Quacrant ocwer Til t is 14.32% wi:hin 2h l
hours a f ter exceecing :nat l imi t or reduce The rmal 3 we r to less than 60% of Thermai ?cuer alicwa:le for the reac:c r coolant pumo comeinaticn wi thin :ne next 2 nours anc recuce the Hign Flux Trio Set:oint to <65.5?: o f The rma l ?cwe r allowable for the reae:ce coolant cumo ecmcination within the nex k hcurs.
3 Identi fy and correct :ne cause of the cut of limit cc odi:icn l
prior to increasing Thermal Dewe r: sucsecuen: 2cwe r 0:e ra t io n above 609 o f Thermal sewer allesao le for :ne reac:ce ecolant i
s pumo ccmoinatien may creceec arevi:ed :na: the 0.uaccan: ewe r i
Tilt is ve ri fiec ;*.923 at least ence :er neur fe r 12 hcurs or until veri fied acce ta:le at 956 or grea:er Ratec Ther al l
Powe r.
A=end:en: No. 26 3-3,.
RANCHO SECO UNIT I TECHNICAL SPECIFICATIONS Limiting Conditions for Coeration B.
With the Quadrant Power Tilt determined to exceec 11.073 but less than 20%, due to mi sali gnment of eitner a safety, regulating or axial power snaping roc:
1.
Reduce :hermal :ower at leas: 2% for each 14, or fraction thereof, of Quadran: Pcwer Tilt in excess of 4.92% witnin 30 minutes.
2.
Verify that the Quadrant Power Tilt is 111.07% within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after exceeding :nat limit or recuce Thermal Power to less than 60% of Thermal Pcwer allewaole for :ne Reac:ce Coolant Pumo c moination within the nex: 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and reduce the High Flux Trio Set:oint to 165.5% of Ther al Power allowable for :ne Reactor Coolant Pumo ecmoination uitnin :ne next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
3 Identify and correct the cause of :he cut of limi c:ndition prior to increasing Thermal Power; sucsecuent Dewer 0:eration above 60% of Thermal Power allcwaole for ne Reac:Or Coolant Pump combination may oroceed proviced :nat the quadrant Power 4
Tilt is verified 1 92% at least once per hour for 12 neurs or until verified acceptacle at 95% or greater Ratec Thermal Power.
C.
With the Quadrant Power Tilt determined to exceed ll.07% but less than 20%, due to causes other than the misalignment of ei:ner a safety, regulating or axia'l pcwer snaping red:
1.
Reduce Thermal Power to less than 60% of Thermal Power allowable for the Reactor C olant Pumo cce:ination witnin 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and reduce the Hign Flux Tri: Set oint to 165.7% of Thermal Power allowaole for the Reac:Or Ccolant Pumo combination within :ne nex: a neurs.
2.
Identify and correct the cause of :. e cu: of limit concition prior to increasing Thermal 3cwer; sucsecuent Pcwer 0:eration above 60% of Thermal Pcwer allowable for :ne Reactor Ceciant s
Pump comoination may proceed crovidec :nat :ne quacrant ower Tilt is verified 1 921 at least once :er hour for 12 neurs 4
or until verifiec at 95% or greater Rated Thermal Power.
D.
Wi:h the Quadran: Power Tilt determined to exceed 20%, a controlleo snut cwn shall e initia:ec immediately anc :ne reactor shall =e Orcugnt to the hot snu down c:ncition wi:nin 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
A=end= enc No. 26 3-323
RANCFO SECO UNIT I TECHNICAL SPECIFICATICNS Limiting Conditions for 0: erat:cn E.
Whenever :ne reac:or is brougn: to not snu::cwn oursuan: :o 3 5.2.4.0 acove, suosecuen: reac:ce ::eratic.- is =ermi::ec for the purpose of measurement, testing arc correc:ive act; n
{
provided :ne :nerma l =cuer anc =c..er range,ign flax se::cin:
l allowable for the Reac:Or Ccclan: J um: ccm:ination are res:-;c:ec i
by a reduction of 2 percent of maximum allo aaie :ower for eacn I, tilt, or fraction thereof, for the xaximum :ilt ooservec prior to shutdown.
F.
The Quadrant Power Tilt shall be determined to :e wi:nin the limits at least once every shift curing operation acove 15:; of l
Rated Thermal Pcwer except onen :ne quacran: Power Til: alarn 8
is inoperacle, then the Quacrant Power Til: snall te caiculatec and evaluated at least once every 2 noers.
3.5.2.5 Control Rod sitions A.
Technical Specification 3.1.3.5 (safety ree wi thcrawal) :ces not pronicit the exercising of incividual safety rocs as required by Table 4.1-2 or acoly to incoeraole safety rec limits in Technical Specification 3.5.2.2.
S.
Operating red group overlao snall be 25 =ercent, +5 percen between three sequential groups, except for pnysics tests.
C.
Posi~ tion limi ts are speci fied for regulat:ng ano axial ecwer shaping centrol reds.
Excect for ;nysics tests or exercising control rods, :ne regulating centrol roc insertion /witnerawal limits ar e soecifiec on Figures 3.5.2-1 threcgn 3.5.2-6.
Also i
excepting pnysics tes:s or exercising control reds, :ne axi'al power shaoing control rod insertion /witncrawal limits are specified on Figures 3.5.2-7 anc 3.5.2-3.
If any of these control red posi:icn limits are exceecec, correc:ive ?easares shall be taken imreciatelv c: acnieve an acce :acle c0ntr:1 rod position. Acceptacle centrol eco ;csi:; ens snall :e attained wi:nin :wo nours.
D.
Except for anysics test, ocwer snali not ce increased acove the power level cutof f of 32 percent of :ne taximum alicwa:le power level unless one of tne fellcwing concitions is satisfied:
1 Xenon reactivity is within 10 :ercen: Of :ne ecuilibrium value for coeration at tne maximum allewa:ie :cwer level and asymptotica l ly approacning s :acil i ty.
2.
Except for Xenon free star:uo, onen 3 5 2.5D(1) acclies, the reac:ce has coeratec..itnin a range of 37 to 52 percent of :ne maximum allewa:le :cwer for a :erico exceeding 2 9 curs in the soluole poisen c:ntrol ecce.
Amendmen: No.
26 3-3-2
RANCHO SECO UNIT I TECHNICAL SPECI FICATICNS Limiting Conditions for Operation 3.5.2.6 Reactor :ower incalance snall :e mcnitorea on a frecuency not to exceed two hours curing =c.,er coerat ion a ove 40 :ercent ratec power.
Exce:t for :nys ics tes ts. i ca l ance s na l i e ma in ta ined within :ne enveicce cefinec sv Tigures 3.5.2-9, 3.5.2-10 anc l
3.5.2-11, if ene imcaiance is,0: wi:nin :ne envele:e :efinec my Figures 3.5.2-9, 3.5.2-1] and 3.5.2-li, corrective easures snall 8
be taken to acnieve an ac:accaole imoalance.
I f an acceptacle imcalance is not ach ievec wi thin two nours, reac:or power shall be recuced until imbalance limits are met.
3 5.2.7 The control rod drive paten :anels shall be locked at all times with limited access to :e autnori:ed by :ne superintencent or nis desig-nated representative.
Bases The power-imoalence enveloce defined in #igures 3.5.2-9, 3.5.2-10 and 3.5.2-11 are basec on LCCA analyses anien have cefinec :he maximum linear nea: rate sucn that the maximum clad tem:erature will not exceec the Finai Acceotance Criteria.3 Correc:ive measures will de :aken snoulo tne incicated quadrant tilt, reo position, or imbalance e cutside :9eir scecified coundary. Operation in a situation tnat would cause the Final Acceotance C.-i teria to be aoproacned snould a LCCA cc:ur is highly imorobacle because all of the pcwer distribution parameters (quadrant tilt, rod positien, and imoalance) must be at their limits while simultaneously all other engineering and uncertainty fac: ors are also at tneir limits.**
a.
Nuclear uncertainty factors b.
Thermal calibration uncertainty c.
Hot red manufac:uring tolerance fac: ors d.
Fuel densi fication ef feces The conser/acite applica:icn of the above peaking augmentation fac: ors co= pen-sates for :ne :otantial peaking penal:y due :o Ee l rod b ow.
The 25% + overlac cetween successive centrol rec grou s is allowed since the worth of a roc is lower a: :ne u::er and Icwer par of tne s:roke. Control rocs are arrangec in groups or sanks cefined as fol!cws:
l Groua Function i
Safety 2
Safety 3
Sa fe ty 4
Safety 5
Regulating 6
Regulating 7
Regulating 8
APSR (axial power shaoing grouo) x* Actual ocerating limits cecend en ane:ner or not incere or exc0re detec:crs are usec and ineir rescec:ive instrument cal ibra t ion errors. The methoc useo to define the ccerating limits is cefined in plant coerating procecures.
Amendment No.
26 3-33a
RAHCHO SECD U":T 1 TECHNI CAL SPECI FI C \\TI CMS Limi ting Condi tiens for Operation t
The red Ocsi tion limits are based en the mcs: limiting of :ne follaving :hree criteria: ECOS Ocwe r ceasi ng. snu::cun margin. anc :oten ti al ej ec:ed rod oor:n.
The re f o re, Ocmo l i ance wi th :ne ECCS pc..ee ce as i ng :-i :2 r i :n is ensured y :ne red posi tion limits.
The minimun avaiiaele roc nortn, corsi s:ent wi:n :ne cc j
position limits, orovices for acnieving not shutccwn :y reac:or trip at any j
roc that is witncrawn remains in :ne t i me, assuming ina(ni gnes t wor:n con trol I)
The roc posi tion limits also ensure tna: inserted roc l
full cut position.
rated ocwe r.i groups will not contain single roc wor:ns grea:er than 0.65a ;k/k at These values have Deen snown to be safe cy the safety analysis of nynothetical roc!
ejection accident. (2)
A maximum singie inserted control red wce:n of 1.0i ik/k single inser:ed is alicwec by tne rod cosi tion limi ts at not ze ro = cue r.
r centrol rec wer:n of 1.03 ak/k at beginning-of-life, nct :ero ocwer aculd resul:
tnermal power ano, :ne refore, less severe environmental -
in a loner transient cean rated Ocwer.
~
consequences than an 0.65% ik/k ejected roc worth at Control rod greues are wi thdrawn in sequence beginning with Orcue I.
Graues The normal pcs i tion at ecwe r i s for 5, 6 and 7 are overia cee 25 :er:ent.
Group 7 to be partially inserted.
The Quadrant Power Til limits set forth in Speci fication 3.5.2.4 have been
{
establisned to prevent the linear heat rate peaking increase asscciated ai:n l
fecm exceecing a posi tive quacrant power :il t during normal pcwer caeration 7.364. The limi:s in speci ficatien 3.5.2.4 are measurement system incecendent.
The ac:ual operating limi ts, wi th tne accrocriate al!cwance for coservacili ty and i ns trumentation errors, for eacn T.sasuremen t sys tem are cefined in the station coerating procecures.
imealance meni toring i n Soeci fi cat ions 3.5.2.LF The quaaran: Til: and axial i n the c recess ccmouter.
and 3.5 2.6, rescec:ively, ncrmally will be cerformed for meni: ring these quanti ties will provice adecuate The two-ncur f requency surveillance unen :ne corouter is cut of service.
Allowance is provi ced for wi thdrawal limi:s and reactor =cwer imoalance scecifica:icn limi:s :o be exceeceo for a cerica of rac neurs wi tncut Acceptac le rod =cs i :icns and imbalance must ce acnieved within violation.
the two-nour time period or appeceriate action sucn as a recuction of cover taken.
Operating res tri cticns are incluced in Technical Sceci fica:icns 3.5.2.5.0.(D and excessive =cwer peaking by transien: eenon. The xenon 3 5. 2. 5 0.CD to creven ei:ner be :evenc :Pe "ancersncot" regicn anc asycocotically reacti vi ty mus:
at ratec Ocver or :ne reac:ce mus: ce acercacning its ecuilibrian value operated in :ne range of 37% :o ?:$ of :ne maximum altavacle :cuer for ane pe ri ce exceeci ng r..o hours i n :ne solc le pcisen con:rci mode so :nat transient :eaA is surnec out at a I cs.e r g ewe r level.
REFERENCE 5 lll FSAR, Secticn 3.2.2.1.2 (2}FSAR, Section 14.2.2.4 (3)sAw-14no se: tee =er lo73, ? age 7-3 Amend:ent No.
26 3-336
Figure 3.3.2-1.
Red Index 'Is ?:t er ' evel f:r Tour-j Pu :p Operata:n. 0 to :s0 EF D n3 l
t72.132 30 137 "' 22 22 I
253 12
$3
- 7ttart
- 1 807 at' st]
IN THi! ;[*;:1 l
13 4EIttt !E3 253 33 41;i",N 73 l
2 l HUT:01
=
Lt'iT 3 63
\\
=
==
M W
,g 43 PERui::Ist! FERATING
- 3 REEL
- N 23 0.15 13 3
3 23 43 63 33 133 1:3 143 f63 133 203 ::: 243 l33 !!G 203 8"'""'
Groua 7 Grouo 5 3
- S 53 75 1C3 3
25 53 75 100 Group 6 3
25 53 15 133
.Ltendment No.
26
Figure 3.5.2-2.
Red :ndex 7s Power Level for Feur-Pump Cperattan. 1-0 :s :?C IF?
n!D ggg 241.102
".3 13:
IIU II "
13 OP!.11 T ' 1 C it':sE3 IN Ni! Af i:1 13
.55.33 10 INui"Ctm Llulf 8E!itic!E3 4tGICN O
10 E
50 14.53 232 10 i
ee i
i 40 32 PERE!::13L! :P!Rath; 20 RE: LCM i
42 15 30 '
{
o.!J 3
i 0
23 40 50 30 te3 1:3 140 its 133 :*3 ::3 :40 :t3 :!: 3:3 Groua 5 esa inae Greuo 7 '
j i
i i
3 25 53 75 100 3
25 53 75 ICO l
Group s 8
25 53 15 103 f
. bend =ent No. 2g
Figure 3.5.2-3.
Rod Idex '.'s Power Level f:e Tour-Pump 0; era: ion. 271 :s 3'O T?D 110 253 4 102 igg OPERaf!O4 %3T ALL3tE3 11 I'l IGI int $ tE !*1
!!! ! 32 33 4.#*
13 IMUTC tM 6g I's.:
Llulf Q""
13 O
O 53 w
SG 14.53 PERWi!$1 ELE CPERail4G 7
REGICM 40 23 23
- CTE: m!S
- IOU:E VALIC Oa.Y *CA :"PERAT:CJ 42.15 AFTER APSA WI X M aAL 10 0.10 3
O 23 43 53 33 103 1:3 140 150 183 ::3 !!3 240 l53 I!3 233 Group 5 asa inces Groua 7 i
i g
to 13 100 3
IS 53 IS
'G3 Grouc 6 3
23 13 75
'M Amendment No. 26
t figure 3.5.2-a.
Red Incex '.'s ? ver Level f or Three-Pump Operat*on. C to '50 i??D 110 i
igg 172.102 258.132 -
'2:3 102 CP!447fC1 40' tit:#E3 go IN *Hl! I!;;0N
[
83 I 70
!H'JT3:14 \\
Llulf i
als RICit: 9E 10N 232.54
[-
60 t
- 10
- 47. 0
[ 40 PERat:31tLE OPERAfl40 AEGICM
- 3 - 3.15 10 0
i l
3 to 40 50 40 IC3 ~123 140 153 183 :3 2:3 24Q 253 :13 203 Grouc 5 988 laats
.Groua 7 9
25 SG T5 100 3
21 53 75 102 Group 6, _
h i
l A=ene.=ert: !;o. 26
5 Figure 3.3.2-5.
Red Index 'Is ?cuer ' evel f or Bree-Pump Cpers::an.
'a :s 290 ET?3 113 265.1:2 133 241.132
- .I32
- PtpattN M0T ALL:tE:
30
~
tN IN11 4[:1:N 83 yg IMUTCCIM Uutt 3
t!!ftl Cit 3 232.54
+3 REG;CM 53 14.53 1
43 33 PERul:L:it ?!9AffN:
.g REGICM N
42.I5 13< 0.10 3
23 43 $3 13 133 I:3 143 153 183 233 2:3 243 253 li3 233 Groua 5 too Ince G, roua,7 53 75 133 Grouo 6,*
Amendment No. 26
Figure 3.3.2-6.
7.0d :.-d a.- Vs Power Level for Three-Pump Operstten. 270 :s 31J ET?3 113 ggg 241.112
- "3.t02 QPtillfiON 40f 33 Ati*st3 14 TW13 4 t Cl *.%
13 10 T
3 60 13 4.50 PERillsstELE :PEParlN3 g
REGl3N 43 33 23 42.15 lg, PCTE: Th!S FIGLRE VA4 ;O OLY 7"'A CF7 RATIO 4 O.10 ApTgg Apsa agTH;gAnAt.
g 0 23 43 63 33 103 1:3 140 16J 180 2:3 223 243 ;63 l33 3:3 Grovo 5 Group 7 i
6, 3
25 13 15 133 3
25 53 75 133 Group 6 t
t r
3 23 53 75 133 Amenci=ent No.
25
e Figure 3.3.2-7.
A?! A :JL:hdravs1 'Is ? ave-I Lasel. 0 :s 'oO I??O i
l 110 (S 0 ! :
(32 3.132) 100 90
,(8 3.32)
(35 3.32)
RESTRIOTE:
REGICN gg<_s] 3.30)
(41.8.30) 2 2
70 2
3 60 PERMISSISLE OPERATING
-a 50 REGION (100.0.50) 2 40 30 20 10 g
e 0
10 20 20 to 50 60 70 a0 33 100 APSR fita::rawal, e
.t:endment No.
26
l Tigure 3.5.2-1.
A?!R 21:5.drasai 'Is ?e.ee Level. '40 :s ?0 I??O 110 j
(3 0.102) 22 3.:32)
I 100 90 I
RESTRICIE2 50 - (3 0. !0)
(45.3.30) 70 E.
=
60 2
=
~
PERMISSISLE (100.50)
OPERATING 40 REGION o
B 2
30 20 NOTE. OPERATICN IF'E9 230 EFF0 Valla CNLY FCR APSR IITHORAAAL 10 g
0 10 20 30 40 50 50 70 50 30 103 APSR ti tnaraeat. ;
A=end=ent No. 26
Fit re 3.5.2-9.
Care L-salance '.* ?:ver 6
Level, C :s '60 ITF0 l
i
( 14 0.102,',
22 '.102) 100 RESTRt0!!3 l
I
( -1
- 3... )
(22.3.32) 3.
n
.E...N s w.c SG 1
I S3 c28.3.33) l (33.4.30)
I i
70 l
1 3
su PERMI SSI RE
=
OPERA!!NG
,0
< ( 49.3.50)
REGION (53.5.50) 40 d
I i
20 20 I
l 10 1
I I
0 40 50 40
-30 20
.r 1 0
10 20 30 40 50 $3 Core Imnalance, t o
A= enc!=en t "o.
26
f Figure 3.5.2-13.
C,s r e I.. balance 'Is ?cear Level, l'0 :o ?O ETP:
110 a
100
( l8.3.102) i:: 3.10:)
I IIIUII2
'C 11 7.32)
(22.3.32) 90 REGICN I
$0
(.3g 0,30) l
(;g.4,33) 1 2
70 l
3 1
50 PERMISSf 31.E OPERATING
=
,0
( 50.0.50)
REGICN
( 53. 5. 50 ',
{
3 40 l
o 1
30 l
1 20 g
i 10 -
g I
0 40
-50
-40 30
-20 10 0
10 20 30 40 50 50 Care Imotance. '
Ac:end:: lent No. 26
Figure 3.5.;-11.
C:re Isralar.ce 'Is ?:ver Level. 07C. :o 3.; E7?:
110 t
( 32 1.102'
,,,ty) 100
[
(I3 # 32) 30
[~'~
(13.5.30) 80 t -42. 33 )
q( 7;,.7(
I RE3 ION 2
70 I
2 PERMt:51BLE I
5 50 CP!3MIT I
a RE310N l
I
( -49. 2. 50 )
(29.1.50) o 5G o
l 0
40 1
I C
l A
a 30 l
mi Ats *IcLas nt::: sa.y :a "PGA*;Ci AFM a?SR 20 w!TH; raw At.
10 g
40 40 40 20
-20 10 0
to 20 20 40 50 50 Care 1:nca1ance. "
se A=endment No.
25
Figure 3 5.2-12 LCCA LIM!TED,"AXI.-UM ALLC'4ASLE LINEAR HEAT of,TE 21 l
20 19 sx 18 3
J
/
I N
3 17
/
!\\
/
_oa 15 E
14 e
3 7
2 13 12 0
2 4
6 8
10 12 Axial Location of Peak 8:wer Freci Settem of Core, f t.
Amendment No. 26
._