ML20054B787
| ML20054B787 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 04/12/1982 |
| From: | SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | |
| Shared Package | |
| ML20054B781 | List: |
| References | |
| NUDOCS 8204190197 | |
| Download: ML20054B787 (7) | |
Text
.
C POWER DISTRIBUTION LIMITS r[ '
h,h'* y l]{T,f 3/4.2.3 RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FALiOx LIMITING CONDITION FOR OPERATION 3.2.3 The combination of indicated Reactor Coolant System (RCS) total flow rate and R, R shall be maintained within the region of allowable operation
{:?..
shownonFlgur 3.2-3 for 3 loop operation.
~
Where:
N" a*
R1 = 1.49 [1.0 + 0.2 (1.0 - P)]
R 3
b.
R2
[1-R8P(BU)] '
THERMAL POWER p,
RATED THERMAL POWER Fh=MeasuredvaluesofF obtained by using the movable incore N
d.
~
detectors to obtain a power distribution map.
The measured values of F shall be used to calculate R since Figure 3.2-3 includes measurement uncertainties of ttSag.for flow and 4% for incore measurement of F", and 2*
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l RBP (BU) = Ro.d Bow Penalty as a function of region average burnup as e.
shown in Figure 3.2-4, where a region is defined as those assemblies with the same loading date (reloads) or enrichment (first core).
APPLICABILITY: MODE 1.
ACTION:
With the combination of RCS total flow rate and R), R utside the region of 2
acceptable operation shown on Figure 3.2-3:
kI a.
Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> either:
1.
Restore the combination of RCS total flow rate and R),
R to within the above limits, or 2
2.
Rede::e THERMAL POWER to less than 50% of RATED THERMAL F0WE?.
('
and reduce the Power Range Neutron Flux - High trip setpoint to less than or equal to 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
8204190197 820412
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CONTAINMENT SYSTEMS A
SURVEILLANCE REOUIREMENTS
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4.6.1.3 Each reactor building air lock shall be demonstrated OPERABLE:
a.
Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following each closing, except when the air lock is being used for multiple entries, then at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, by verifying that the seal leakage rate is less than or equal to 0.01 L when the volume between the door seals is pressurized to
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greatef than or equal to 8.0 psig for at least -2
- ce..d;.
., m.., +-s By conducting overall air lock leakage tests at not less than P,,
b.
47.1 psig, and verifying the overall air lock leakage rate is within its limit:
1.
At least once per 6 months #, and 2.
Prior to establishing CONTAINMENT INTEGRITY when maintenance has been performed on the air lock that could affect the air lock sealing capability.*
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c.
At least once per six months by verifying that only one door in each
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air lock can be opened at a time.
d.
e Ie d -ce te~
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6 ve<419 %d the sa I leak-se vale is Iscr $an e 7 l fo av o,o l L, ulian
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.S kc, ff s e e ls is e g u e. l -l0 T.O psig
$v ah lee.sf 2 minde.%
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- The provisions of Specification 4.0.2 are not applicable.
- ~Exemotion to Appendix J of 10 CFR 50.
!(
SUMMER - UNIT 1 3/4 6-5
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REFUELING OPERATIONS 3/4.9.11 SPENT FUEL POOL VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.9.11 l Two independent spent fuel pool ventilation sub-systems shall be OPERABLEjaith ;t 1;;;t ens ;ut ;j;tc.T in ep;r;ticr.
APPLICABILITY: Whenever irradiated fuel is in the spent fuel pool.
ACTION:
With one spent fuel pool ventilation sub-system inoperable, fuel a.
movement within the spent fuel pool er cran; ;;;r;ticr with 1;;d;
- vcr th
- p;nt ft:1 p;;l may proceed provided the OPERABLE spent fuel pool ventilatio.n web-system is capable of being powered from an OPERABLE emergency power source and is in operation.:rd di :h:rgim; through at le::t :n: trai Of 9EP^ 'ilter: :nd charce:1 2d: rbert.
b.
L'ith a; :p;nt f t:1 pool vent 1stier :tb-cyct:: OPER^SLE, cu: pend :l' 4
- peration: '
l"* g :cerent Of fuel it54-th: : pent iu:1 p::1. ;r cran; op;r;ti;n with 1 :d: Over th: pent ft:1 pt:1
- h. pt The provisions of Specification,4 0.4 are not applicable.
3 2.*3 *d SURVEILLANCE REOUIREMENTS 4.9.11,( The above required spent fuel pool ventilation +wb-systems shall be demonstrated OPERABLE:
t At least once per 31 days on a STAGGERED TEST BASIS by initiating, l
a.
from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that each ewb-system operates for at least 15 minutes.
b.
At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the system by:
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SUMMER - UNIT 1 3/4 9-12 l
l
REFUELING OPERATIONS
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3/4.9.11 SPENT FUEL POOL VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION At leab osse 3.9.112 Tn/i.,dspo..e,,t spent fuel pool ventilation rub-system $ shall be r
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APPLICABILITY: Whenever irradiated fuel is# n the spent fuel pool.
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a, With no spent fuel pool ventilation entr-system ^0"""*"L:, suspend all A-operations involving movement of fuel within the spent fuel pool -et-pent fu ' p:to#1 y kt..rfe.d 4.e/
- 1.
--'icr with 1 :d; c';Cr th:d f.
pool ve:dp-lM/*n CrcrC operef
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The provisions of Specification 3.0.4 are not applicable.
g 2.0.3 and SURVEILLANCE REOUIREMENTS 4.9.1L2.The above required spent fuel pool ventilation seta system $ shall be a_____.__.
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SUMMER - UNIT 1 3/4 9-Pf/4 I
- (
POWER DISTRIBUTION LIMIT BASES
-' S HEAT FLUX HOT CHANNEL FACTOR and RCS FLOWRATE and NUCLEAR -ENTHALPY RISE HOT CHANNEL FACTOR (Continued)
(.
- c.. The-control rod insertion limits of Specifications 3.1.3.5 and
^3.1.3.6 are maintained.
- . d.
The 'axialdower^distribtition, expressed in terms of AXIAL FLUX
. DIFFERENCE, is maintained within the limits.
s.
F will be mai~ntained within :its limits provided conditions. a. through g
- d. above are maintained. 'As noted on Figures 3 2-3 and 3.2-4, RCS flow rate and Fh may be " traded off" against one another (i.e., a low measured RCS flow rate is acceptable if the measured Fh -is also low) to ensure that the calculated DNBR will not be below the' design}DNBR value, The relaxation of__. _
FhasafunctionofTHERMALPOWERallowschangesintheradialpowershape for all permissible rod insertion limits.
r:-
R, as calculated in 3.2.3 and used in Figure 3.2.3, accounts for F H 1
.......Th s value is used in the 'various accident i
-/
less than or equal to 1.49.
fQ ga..
(
analyse,s where FcH..i.n.fluen.ces. para. meters other than DNBR, e.g., peak clad
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temperature and thus is the maximum "as measured" va1ue allowed.
R ' 'S 2
l defined, allows for the inclusion of a penalty for rod bow on DNBR only. Thus knowingth'is"asmeasured"valuesofFfH and RCS flow allows for " tradeoffs" in excess of R equal to 1.0 for the purpose of offsetting the rod bow DNBR penalty.
When an F measurement is taken, an allowance for both experimental error q
I
~ and manufacturing tolerance must be made. An allowance of 5% is appropriate for a full core map taken with the incore detector flux mapping system and a
(
3% allowance is appropriate for manufacturing tolerance.
The radial peaking factor Fxy(Z) is measured periodically to provide assurance that the hot channel factor, F (Z), remains within its limit. The RTP)0as provided in the Radial Peaking F
limit fer Rated Thermal Power (Fx xy b
Factor Limit Report per specification 6.9.1.14 was determined from expected power control maneuvers over the full range of burnup conditions in the core.
N When RCS flow rate and F are measured, no additional allowances are.
g necessary prior to comgapigon with the limits of Figures 3.2-3 and 3.2-4.
N Measurement errors of '. 5% for RCS total flow rate and 4% for FON have been allowed for in determination of the design DNBR value.
MAR 03.1Sgg SUMER - UNIT 1 B 3/4 2-4
-