ML20154B996
| ML20154B996 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 09/07/1988 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML20154B982 | List: |
| References | |
| NUDOCS 8809140208 | |
| Download: ML20154B996 (31) | |
Text
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b INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PACE 3/4.2 PO*='IR DISTRIBUTION LIMITS 3/4.2.1 Axial Flux Difference..................................
3/4 2-1 3/4.2.2 Heat Flux Hot Channel Factor............................
3/4 2-5 3/4.2.3 Nuclear Enthalpy Hot Channel Tactor.....................
3/4 2 9 3/4.2.4 Quadrant Peve's Tilt Ratio...............................
3/4 2-12 3/4.2.5 DNB Parameters..........................................
3/4 2-14 1
3/4.3 INS 1PtHENTATION 3/4.3.1 RIACTOR TRIP SY STEM INSTRUMENTATION.....................
3 /4 3-1 3/4.3.2 ENGINEERED SATETY TEATURE ACTUATION SYSTEM INSTRUMENTATION 3/4 3-15 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring....................................
3/4 3-35 l
Movable Incore Detectors................................
3/4 3-39 S e ismic Ins t rumenta t ion.................................
3 /4 3-40 l
Me teorological Inst rumenta tion..........................
3/4 3-43 Auxiliary Shutdown Panel Menitoring Instrumentation.....
3/4 3-46 Accident Monito ring Ins t rumentation......................
3 /4 3-49 Tire De t ec t ion Ins t rument a t ion..........................
3 /4 3-5 2 Loose Parts Monitoring System...........................
3/4 3-56 j
Radioactive Liquid Ef fluent Monitoring Instrueentation..
3/4 3-58 Radioactive Gaseous Ef fluent Monitoring Instrumentation.
3/4 3-65 t
3/4.4 REACTOR COOLANT SYSTEM l
l 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION i
Startup and Power operation.............................
3/4 4-1 l
HotStaedby.............................................3/44-2 S hu. d e vn................................................
3 / 4 4 - 3 i
I s o l a t e d Lo op...........................................
3 / 4 4 -4 Isolated Loop startup...................................
3/4 4-5 NCRnl ANNA - UNIT 1 IV Amendnent No. J. 20. JJ,4 3,105 8807140200 000907 PDR ADOCK 05000330 P
PNU
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4 s
i T
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i INDtx
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I LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIRDitNTS t
a
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SECTt0N g
1 i
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3/4.11 RADICACTIVE IFFLUENTS i
i 3/4.11.1 LIQUID ETTLUENTS
(
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Concentration.............................................
3/4 11-1 l
Dose......................................................
3/4 11-5
]
Liquid Radweste Treatment.................................
3/4 11-4 Liquid Holdup Tanks.......................................
3/4 11-7 4
a I
3/4.11.2 CASEQUS ITTLUENTS l
Dose Rate.................................................
3/4 11-4 Dose-Noble C4ses..........................................
3/4 11-13 j
]
Dose-Iodine-131. Trittua and f
Radionuclides in Particulate Tora.........................
3/4 11-14
)
Caseous Radvaste Treatment................................
3/4 11-15 Ex p le s iv e c a s M 1x t u r e.....................................
3/4 11-16 l
Cas $torage Tanks.........................................
3/4 11-17 f
e t
3 /4.11. 3 $0 LID RADICACTIVE VASTE...................................
3/4 11-18
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1 3/4.11.4 TOTAL D0$t................................................
3/4 11-19 Iy
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j 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING J
l 3/4.12.1 MONITORING FR0 CRAM......................................
3/4 12-1
-1 3/4.12.2 LAND U$t CENSUS.........................................
3/4 12-13
)
i 3/4.12.3 !NTERLA)0RATORY C0KFAR!$0N..............................
3/4 12-14 N0Rtil ANNA - UNIT 1 XI A344dment NO. I O I
4
INDEX BASES SECTION Page 3/4.0 APPLICABILITY.............................................
B 3/4 0 1 3/4.1 REACT!VITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTR0L........................................
B 3/4 1-1 3/ 4.1. 2 BORATION SYSTEMS........................................
B 3/4 1-2 3/4.1.3 MOVABLE CONTROL ASSEM8 LIES..............................
B 3/4 1-4 3/4.2 POWER O!STRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE...................................
B 3/4 2-1 3/4.2.2 and 3/4.2.3 HEAT FLUX AND NUCLEAR ENTHALPY HOT CHANNEL FACT 0RS.........................................
B 3/4 2-4 3/4.2.4 QUADRANT POWER TILT RAT!0...............................
B 3/4 2-5 3/4.2.5 DNB PARAMETERS..........................................
9 3/4 2-6 l
l i
1 1
l l NORTH ANNA - UNIT 1 XII Anendment No. 4 3), 105
r l
3/4.2 POWF.R O!STR!sVTION LIMITS AXIAL FLUX O!FFERENCE (AFD)
LIMITING CONDITION FOR OPERATION the allowed operational space defined by Fig (AFD)3.21 l
t 3.2.1 The indicated AXIAL FLUX DIFFERENCE shall be maintained within ure 1
APPLICA8!LITY: MODE 1 A80VE 50% RATED THERMAL POWER l
ACTION:
a.
With the indicated AXIAL FLUX O!FFF.RENCE outside of the Figure 3.2 1 limits, I
1.
Either restore the indicated AFD to within the Figure 3.21 limits within 15 minutes, or l
2.
Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 30 minutes and reduce the Power Range Neutron Flux - Higli Trip setpoints to less than or equal to 55 percent 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 />, b.
THERMAL POWER shall not be increased above 50% of RATED THERMAL POWER unless the indicated AFD is within the Figure 3.2 1 limits.
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t NORTH ANNA. UNIT 1 3/4 2 1 AmendM nt No. 3. 5. 27 77. 63, 105 i
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POWER DISTRIBUTION LIMITS LIMITING CUN0! TION FOR OPERATION (Continued) 1 l
SURVE!LLANCE REQUIREMENTS l
4.2.1.1 The indicated AX!AL FLUX O!FFERENCE shall be t' termined to be within its limits during POWER OPERATION above 50% of RATED Th 34AL POWER by:
l l
a.
Monitoring the indicated AFD for each OPERABLE excore channel 1.
At least once per 7 days when the AFD Monitor Alarm is OPERABLE, and 2.
At least once per hour for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after restoring the AFD Monitor Alarm to OPERABLE status, b.
Monitoring and logging the indicated AX!AL FLUX O!FFERENCE for each OPERABLE excore channel at least once per hour for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and at least once per 30 minutes thereafter, when the AXIAL FLUX O!FFERENCE Monitor Alarm is inoperable. The logged values of the indicated AXIAL FLUX O!FFERENCE shall be assumed to exist during the interval preceding eich logging.
4.2.1.2 The indicated AFD shall be considered outside of its limit when at least 2 OPERABLE excore channels are indicating the AFD to be outside of the
' limit shown in Figure 3.2.1.
I NORTH ANNA - UNIT 1 3/4 2-2 Amendment No. If.105
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THis PAGE DELETED NORTH ANNA. Utili 1 3/4 2-3 Amendment No. 16, 105
Figure 3.2-1 is provided in the Core Surveillance Report as per Technical Specification 6,9,1,7 Figure 3.2.1 - Axial Flux Difference Limits as a Function of Rated Thermal Power NORTH ANNA - Ull!T 1 3/4 2 4 Amendment No, 31.105
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POWER DISTRIBUTION LIMITS HEATFLUXHOTCHANNELFACTOR-Fg LIMITING CONDITION FOR OPERATION 3.2.2 F (Z) shall be limited by the following relationships:
q F (Z) 1 [2.151 [K(Z)]for P > 0.5 9
P F (Z) 1 [4. 30] [K(Z)]for P 10.5 q
where P = THERMAL POWER l
RATED THERMAL POWER 1
and K(Z) is the function obtained from Figure 3.2-2 for a given i
core height location.
{
l APPLICABILITY: MODE 1.
l ACTION:
With F (Z) exceeding its limit:
q a.
Reduce THERMAL POWER at least 1% for each 1% F (Z) exceeds the l
q limit within 15 minutes and similarly reduce the Power Range Neutron Flux-High Trip Setp61nts within the'next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; I
POWER OPERATION ma/ proceed for up to a total of 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />sg subsequent POWER OPERATION may proceed provided the Overpower AT Trip.Setpoint (value of K ) has been reduced at least 3
1%'(in AT span) for each 1% F (Z) exceeds the limit, q
b, Identify and correct the cause of the out of limit condition prior l
to increasing THERMAL POWER above the reduced limit required by a, I
above; THERMAL POWER may then be increased provided F (Z) is o
demonstrated through incore napping to be within its Iimit.
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N0hTH ANNA - UNIT 1 3/4 2-5 faendment No. (3),18.Nf, W.
Hi 106
POWER DISTRIBUC_jN LIMITS SURVEILLANCEREQUIrp1ENTS 4.2.2.1 The provisions of Specification 4.0.4 are not applicable.
4.2.2.2 F (Z) shall be evaluated to determine if F (Z) is within its q
q limit by:
a.
Using the movable incore detectors to obtain a power distribution map at any THERMAL POWER greater than 5% of RATED THERMAL POWER.
b.
Increasing the measured F (Z) component of the power distribution n
map by 3% to account for manufacturing tolerances and further increasing the value by 5% to account for measurement uncertainties.
c.
Satisfying the following relationship:
N Fq (z) 1 2.15 x K(z) for P > 0.5 P x N(z)
M K(z) for P 1 0.5 Fq (z) 1 2.15 x
N(z) x 0.5 N
manufackur(z)isthemeasuredF(z)increasedbytheallowancesfor where F ingtolerancesandmkasurementuncertainties,2.15is the F limit, K(z) is given in Figure 3.2-2, P is the relative n
THERMAL POWER, and N(z) is the cycle dependent function that accounts for power distribution transients encountered during normal operation.
This function is given in the Core Surveillance Report as per Specification 6.9.1.7.
N d.
Measuring Fq (z) according to the following schedule:
1.
Upon achieving equilibrium conditions after exceeding the THERMAL POWER at whicn F (z) was last determined.by 10%
O or more of RATED THERMAL POWER *, or 2.
At least once per 31 effective fuli power days, whicheve.r occurs first.
e.
With measurements indicating N
maximum Fq (z) over z K(z) j N
has increased since the previous determination of Fq (z) either of the following actions shall be taken:
"During power escalation, the power level may be increased until a power level for extended operation has been achieved and a power distribution map obtained.
NORTH ANNA - UNIT 1 3/4 2-6 Amendment No.
05
POWER DISTRIBUTIOS LIMITS SURVEIl, ANCE REQUIREMENTS (Continued)
N(z) shall be incr ased by 2% over that specified in 1.
F492.2.2.c,or N
2.
phwe(z)shallbemeasuredatleastonceper7effectivefull F
r days until 2 successive ma s indicate that N
maxinum Fq (z) over z K(z) is not increasing, f.
With the relationships specified in 4.2.2.2.c above not being satisfied:
1.
Calculate the percent Fn(z) exceeds its limit by subtracting one from the measuremenY/ limit ratio and multiplying by 100:
N maximum Fq (z)
-1 x 100 for P > 0.5 over z 1
2.15 x (K(z) i P x N(z)
N maximum Fq (z)
-1 x 100 for P < 0.5 over z 2.15 x (K(z,-
0.5 x N(z) 2.
Either of the following actions shall Le taken:
a.
Power operation may continu. crovided the AFD limits of Figure 3.2-1 are reduced 1% AFJ for each percent F (z) g exceeded its limits, or 5.
Comply with the requiremanh cf Specification 3.2.2 for F (z) exceeding its limit by the percent calculated above.
9 g.
The limits specified in 4.2.2.2.c, 4.2.2.2.e, and 4.2.2.2.f above ars' not applicable in the following core plane regions:
1.
Lower core region 0 to 15 percent inclusive.
2.
Upper core region 85 to 100 percent inclusive.
4.2.2.3 When F (z) is measured for reasons other then meeting the requirements q
of Specification 4.2.2.2, an overall measured F (z) shall be obtained from a n
power distribution map and increased by 3% to account for manufacturing tolerances and further increased by 5% to account for measurement uncertainty.
NORTH ANNA - UNIT 1 3/4 2-7 Amendment No. 16,22,37,83,105
P 1.2
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CORE HEIGHT (Ff) 1 l
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NORMALIZED F (z) AS A FUNCTION OF CORE HEIGHT Figure 3.2-2 g
i N05tTH ANNA - UNIT 1 3/4 g.8 Amendtnent No. 3,$ J$,J),f 5, 84
TABLE 3.2-1 2,
Og DNB, PA_P.AMETERS M
30 LIMITS gg 2 Loops in Operation **
2 Loops in Operation **
3 Loops in
& Loop Stop
& It31ated Loop PARAMETER Operation Valves Open Stop Valves Closed Reactor Coolant System T,yg 1 591 F Pressurizer Pressure 1 2205 psig*
Total Flow Rate 289.200 gpm u
Y G
N aa R
5?
- Limit not applicable during either a THERMAL POWER ramp increase in excess of 5% RATED THERMAL g
POWER per minute or a THERMAL POWER step increase in excess of 10% RATED THERMAL POWER.
}3
- Values dependent on NRC approval of ECCS evaluation for these conditions.
I
2 THIS PAGE DELETED f
IDRTH ANNA - UNIT 1 3/4 2.16 Amendment Ho, 3,5,15.22, 37,39,45.84, 105
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NORTH ANNA - UNIT 1 3/4 2.17 Amendmer'; Na, 3,5,22,37,63,105
THIS PAGE DELETED (NEXT PAGE IS 3/4 3.1)
NORTH ANNA. UNIT 1 3/4 2.18 Amendment No. 3,5,22,37,105
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1 NORTH ANNA. UNIT I 3/4 3J4 Amendment No, J 105
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NORTH ANNA UNIT 1 3/4 3.55 Amendment No. 3.5,105
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L 3/4.10 SPECIAL TEST EXCEPTIONS 1
l SHUT 00WN MARGIN LIMITING CONDITION FOR OPERATION l
3.10.1 The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 may be suspended for measurement of control rod worth and SHUTDOWN MARGIN i
provided the reactivity equivalent to at least the highest estimated j
control rod worth is available for trip insertion from OPERABLE control I
rod (s).
APPLICABILITY: MODE 2.
ACTION:
s.
With any full length control rod not fully inserted and with less than the above reactivity equivalent available for trip inserticn, initiate and continue boration at 3 10 gpm of at least 12.950 ppm l
boric acid solution or its equivale,nt until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.
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b.
With all full length control rods inserted and the reactor sub-I critical by less than the above reactivity equivalent, immediately initiate and continue boration at 3 10 gpm of at least 12.950 ppm l
boric acid solution or its equivale,nt until the SHUTOOWN MARGIN required by Specification 3.1.1.1 is restored.
SURVEILLANCE REQUIREMENTS l
4.10.1.1 The position of each full length rod either partially or fully withdrawn shall be determined at least once per 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
I 4.10.1.2 Each full length rod that is not fully inserted shall be demonstrated capable of full insertion when tripped from at least 50%
withdrawn position within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to reducing the SHUTDOWN MARGIN to less than the limits of Specification 3.1.1.1.
NORTH ANNA - UNIT 1 3/4 10-1 AmendmentNo.48'63-
e p
L SPECIAL TEST EXCEPTIONS GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION 3.10.2 The group height, insertion and power distribution limits of Specifications 3.1.3.1, 3.1.3.5, 3.1.3.6, and 3,2,4 may be sus' ended p
during the performance of PHYSICS TESTS providedt a.
The THERMAL POWER is maintained 1 8S% of RATED THERMAL POWER, and b.
The limits of Specificaticns 3.2.2 and 3.2.3 are maintained and determined at the freauencies specified in Specification 4.10.2.2 belcw.
APPLICABILITY: MODE 1.
ACTION:
With any of the limits of Specifications 3.2.2 or 3.2.3 being exceeded while the requirements of Specifications 3.1.3.1, 3.1.3.5, 3.1.3.6, and 3.2.4 are suspended, either:
a.
Reduce THERMAL POWER sufficient to satisfy the ACTION require-ments of Specifications 3.2.2 and 3.2.3, or b.
Be in HOT STANO3Y within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUICEMENTS l
l 4.10.2.1 The THERMAL POWER shall be determined to be 1 8S% of RATED THERMAL P.0WER at least once per hour during PHYSICS TESTS.
i 4.10.2.2 The Surveillance Requirements of Specifications 4.2.2 and 4.2.3 shall be perfonned at the following frequencies during PHYSICS TESTS.
i a.
Specification 4.2.2 - At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, b.
Specification 4.2.3 - At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
NORTH ANNA - UNIT 1 3/4 10-2 Amendment No. Ys,105
,y_y,._.m..- - - -.. - _.,, _,,,, _ - _,. - _,, - _ _, _., _., _,,.
._.vz_
3/4.2 POWER DISTRIBUTION LIMITS BASES The specifications of this section provide assurance of fuel integrity during Condition I (Normal Operation) and fl (Incidents of Moderate Frequency) events by:
(a) maintaining the minimum DNBR in the core from going beyond the design limit DNBR during normal operation and in short term transients, and (b) limiting the fission gas release, fuel pellet temperature & cladding mechanical properties to within assumed design criteria.
In addition, limiting the peak linear power density during Condition I events provides assurance that the initial conditions assemed for the LOCA aralyses are met and the ECCS acceptance criteria limit of 2200*F is not exceeded.
The definitions of certain hot channel and peaking factors as used in these specifications are as follows:
F (Z)
Heat Flux Hot Channel Factor, is defined as the maximum local 0
heat flux on the surface of a fuel rod at core elevation Z divided by the average fuel rod heat flux, allowing for manufacturing tolerances on fuel pellets and rods.
F Nuclear Enthalpy Rise Hot Channel Factor, is defined as the g
ratio of the integral of linear power along the rod with the highest integrated power to the average rod power.
3/4 2.1 AXIAL FLUX DIFFERENCE (AFD)
The limits on AXIAL FLUX O!FFERENCE assure that the F (Z) upper bound 0
envelope, as given in Specification 3.2.2, is not exceeded during either normal operation or in the event of xenon redistribution following power changes.
t NORTH ANNA - UNIT I B 3/4 2 1 Amendment No. 3.5.16.33 J5,81, 105
POWER DISTRIBUTION LIMITS BASES 1
Provisions for monitoring the AFD on an automatic basis are derived from the plant process computer through the AFD Monitor Alarm. The computer determines the one minute average of each of the OPERABLE excore detector outputs and provides an alarm message immediately if the AFD for at least 2 of 4 or 2 of 3 OPERABLE exes ce channels are outside the allowed al. cower ooerating space and the THERt!AL POWER is greater than 50% of RATED THERMAL POWER.
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l NORTH ANNA - UNIT 1 8 3/4 2-2 Amendment No. 3. 5. 22. 77,105
i THIS PAGE DELETED NORTH ANNA - UNIT 1 8 3/4 2.3 Ame,1dment No. 105
POWER O!STRIBUTION LIMITS BASES 3/4.2.2 and 3/4.2.3 HEATFLUXANDJUCLEARENTHALPYHOTCHANNELFACTORS.
)
N F(Z)andF g
3H l
l The limits on heat flux and nuclear enthalpy hot channel factors j
ensure that 1) the design limits on peak local power density and minimum DNBR are not exceeded and 2) in the event of a LOCA the peak fuel clad temperature will not exceed the 2200*F ECCS acceptance criteria 11: nit.
Each of these hot channel factors are measurable but will nomally only be detemined periodically as specified in Specifications 4.2.2 and 4.2.3.
This periodic surveillance is sufficient to insure that the hot t
channel factor limits are maintained provided:
a.
Control rod in a single group move together with no individual rod insertion differing by more than 112 steps from the group j
demand position.
b.
Control rod groups are sequenced with overlapping groups as described in Specification 3.1.3.6.
i c.
The control rod insertion limits of Specifications 3.1.3.5 and 3.1.3.6 are maintained.
l d.
The axial power distribution, expressed in tems of AXIAL FLUX DIFFERENCE, is maintained within the limits, i
U The relaxation in F asafunctionofTHERMALPOWERallowschanges intheradialpowershapgHfor all pemissible rod insertion limits. F willbemaintainedwithinitslimitsprovidedconditionsathrudaboN, are maintained.
1 When an F measurement is taken, both experimental error and man-n ufseturing tolerance must be allowed for.
5% is the appropriate allowance for a full core map taken with the incore detector flux mapping system
]
and 3% is the appropriate allowance for manufacturing tnlerance.
N The Specified limit for F contginsa4%errorallowance. Normal
]
operation will result in a mesNred F i 1.49 The 4% allowance is basedonthefollowingconsiderationskH
}
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NORTri ANNA - UNIT 1 B 3/4 2-4 Amendment No.16.84 1
t
POWER DISTRIBUTION LIMITS BASES abaormal perturbations in the radial power shape, such as from rod a.
N misalignment, effect F m re directly than F,
AH q
b.
although rod movement has a direct influence upon limiting Fn to wfthinitslimit,suchcontrolisnotreadilyavailabletolYmit F3g, and errors in prediction for control power shape detected during startup c.
physics tests can be compensated for in F by restricting axial flux q
This compensation for Fh is less readily available.
distributions.
Fuel rod bowing reduces the value of the DNS ratio.
Credit is available to offset this reduction in the margin available between the safety analysis design DNBR values (1.57 and 1.59 for thimble and typical cells, respectively) and the limiting design DN8R values (1.39 for thimble cells and 1,42 for typical cells).
The applicable value of rod bow penalties can be obtained from the FSAR.
N The hot channel factor F cycleandheightdependentpohe(Z)ismeasuredperiodicallyandincreasedbya r factor, N(Z), to provide assurance that the limit on the hot channel factor, Fn(Z), is met.
N(Z) accounts for the non-equilibrium effects of normal oper1 tion transients and was determined from expected power control maneuvers over the full range of burnup conditions in the core.
The N(Z) function for normal operation is provided in the Core Surveillance Report per Specification 6.9.1.7.
314.2.4 QUADRANT POWER TILT RATIO The quadrant power tilt ratio limit assures that the radial power distribu-tion satisfies the design values used in the power capability analysis.
Radial power distribution measurements are m60e during startup testing and periodically during power uperation.
The limit of 1.02 at which corrective action is required provides ONB and linear heat generation rate protection with x-y plane power tilts.
The 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 correction of a dropped Tr misaligned rod.
In the event such action does not correct the tilt, the margin for uncertainty on F is reinstated by reducing the power by g
3 percent for each percent of tilt in excess of 1.0.
For purposes of monitoring QUADRANT POWER TILT RATIO when one excore detector is inoperable, the moveable incore detectors are used to confirm that the normal-ized symmetric power distribution is consistent with the QUADRANT POWER TILT RATIO.
The incore detector monitoring is done with a full incore flux map or two sets of 4 symmetric thimbles.
The two sets of 4 symmetric thimbles is a unique set of 8 detector locations.
These locations are C-8, E-5, E-11, H-3, H-13 L-5, L-11 and N-8.
NORTH ANNA - UNIT 1 8 3/4 2-5 Amendment No. 35,89,84, 105
?
POWER DISTRIBUTION L ffi!TS BASES 3/4.2.5 DNB PARAMETERS l
The limits on the DNB related parameters assure that each of the parameters are maintained within the normal steady state envelope of operation assumed in the transient and accident analyses. The limits are consistent with the initial FSAR assumptions and have been analytically demonstrated adequate to maintain a minimum DNBR greater than the design limit throughout each analyzed transient. Measurement uncertainties must be accounted for during the periodic surveillance.
The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> periodic surveillance of these parameters thru instrument readout is sufficient to ensure that the parameters are restored within their limits following load et 'nges and other expected transient operation.
The 18 month periodic measurement of the RCS total flow rate is adequate to detect flow degradation and ensure correlation of the flow indication l
channels with measured flow such that the indicated percent flow will provide sufficient verification of flow rate on a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> basis.
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l NORTH ANNA - UNIT 1 B 1/4 2-6 Amendment No. 3.5.22.37.44. 105
s INSTRUMENTATION BASES 3/4.3.3.6 POST-ACCIDENT INSTRUMENTATION The OPERABILITY of the post-accident instrumentation ensures that sufficient information is available on selected piant parameters to monitor and assess these variables following an accident.
3/4.3.3.7 FIRE DETECTION INSTRUMENTATION OPERABILITY of the fire detection instrumentation ensures that adequate warning capability. is available for the prompt detection of fires. This capability is required in order to detect and locate fires in their early stages. Prompt detection of fires will reduce the poten-tial for damage to safety related equipment and is an integral element in the overall facility fire procection program.
In the event that a portion of the fire detection instrumentation is inoperable, the establishment of frequent fire patrols ir) the affected areas is required to provide detection capability unt the inoperable instrumentation is restored to OPERABILITY.
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t 3/4.3.3.9 LOOSE PARTS MONITORING SYSTEM l
OPERABILITY of the Loose Parts Monitoring System provides assurance that loose parts within the RCS will be detected. This capebility is j
designed to ensure that loose parts will not collect and create undesirable l
flow blockages.
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NORTH ANNA - UNIT 1 B 3/4 3-3 Amendment No. 3.)& 105
INSTRUMENTATION BASES 3/4.3.3.9 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potencial releases of liquid effluents. The alars/
trip setpoints for these instrument: shall be calculated and adjusted in accordance with the procedures in the ODCM to ensure that the alara/ trip will occur prior to exceeding the limits of 10 CTR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CTR Part 50. The purpose of tank level indicating devices is to assure the detection and control of leaks
' hat if not controlled could potentially result in the transport of radtoactive materials to UNRESTRICTED AREAS.
3/4.3.3.10 RADIOACTIVE ctSEOUS ETTLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alars/
trip setpoints for these instruments shall be calculated and adjusted in accordaace with the procedures in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CTR Part 20. This instrumentation also includes provisions for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the vaste gas holdup system. The OPERASILifY and use of this instrumentation is consistent with the requirenents of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.
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NORTH ANNA - UNIT 1 3 3/4 3-4 Amendment No. 4 g
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NORTH ANNA - UNIT 1 6-17 Amendment No. 63
ADMINISTRATIVE CONTROLS CORE SURVEII. LANCE REPORT 6.9.1.7 The N(Z) function for normal operation and the Axial Flux Difference limits (T.S. Figure 3.2.1) shall be provided '.o the NRC in accordance with the applicable provisions of 10 CFR 50.4 at laast 60 days prior to cycle initial criticality unless otherwise approved by the Commission by letter.
In the event that this information would I
be submitted at some other time during the core life, it shall be submitted 60 days prior to the date the information would become effective unless otherwise approved by the Commission by letter.
Any information needed to support N(Z) and/or the Axial Flux Difference limits will be by request from the NRC and need not be included in this report.
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l NORTH ANNA - UNIT 1 6-18 Amendment No. J7 (J, 105
s ADMINISTRATIVE CONTROLS (Continued) l ANNUAL RA0!0 LOGICAL r.NVfRONW
' TING REPORT
- 6.9.1.c Routin-Pa m onzental Operating Reports covering the i
operation of the it e c vious calendar year shall be submitted prior to May 1 of rh m' filtial report shall be submitted prior to i
4 May 1 of the yea, a '
1 criticality.
The Annual Radiologice vital Operating Reports shall include sumaries, interpretations, and a; 11s of trends of the resuli.s of the radiological environmental surveilla activities for the repot t period, including a compar-ison (as appropriate) with preoperational studies, operational controls, and previous environmental surveillance reoorts, and an assessment of the observed l
impacts of the plant operation on the environment. The reports shall also l
include the results of land use censuses required by Specification 3.12.2.
The Annual Radiological Environmental Operating Reports shall include the results of analysis of all radiclogical environmental samples and of all environmental radiation measurements taken during the period pursuant 19 the locations speci-l fled in the Table and cigures in the 00CM, as well as surmrized and tabulated i
results of these analyses and measurements in the fonMt of the table in the l
Radiological Assessmcat Branch Technical Posit %n, Revision 1, Novemor:r 1979.
l' In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results.
The missing data shall be submitted as soon as possible in a supplementary report.
I The reports'shall also include the following:
a sunnary description of the radiological envirormental r.onitoring program; u least two legible maps" covering all sampling locations keyed to a table giving distances arid directions from the conterline of one reactor; the results of licenset participation in the Interlaboratory Comparison Program, required by Specificacion 3.12.3; discussion of all deviations from the sampling schedule of Table 4.12-1 and discussion of all analyses in which the LLO required by Table 4.12 3 was not achievable.
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- A single submittal may be made for a multiple unit station.
"One map shall cover stations near the SITE BOUNDARY; a second shall include the more distant stations.
NORTH ANNA-UNIT 1 6-19 Amendment No. J/, 4, gg,(tf,105
ADMINISTRATIVE CONTROLS (Continued)
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT
- 6.9.1.9 Routine Radioactive Effluent Release Reports covering the operation l
of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year. The period of the
(
first report shall begin with the date of initial criticality.
)
The Radioactive Effluent Release Reports shall include a sunnary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radio-active Materials in Liquid and Gaseous Effluents from Ligh.-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data sunnarized on a quarterly basis following the format of Appendix B thereof.
The Radioactive Effluent Release Report shall be submitted within 60 days after January 1 of each year.
This report shall include an assessment of the I
radiation doses to the maximum exposed MEMBERS OF THE PUBLIC due to the radio-active liquid and gaseous effluents released from the unit or station during the previous calendar year. Annual Meteorological data collected over the previous year shall be in the fonn of joint frequency distributions of wind speed, wind direction, and atmospheric stability. This meteorological data shall be retained in a file on site and shall be made available to the NRC upon request. All assumptions used in makin l
cific activity, exposure time and location) g these assessments (i.e., spe-shall be included in the OFFSITE I
DOSE CALCULATION MANUAL (00CM). Concurrent meteorological conditions or l
historical annual average atmospheric dispersion conditions shall be used for determining the gaseous pathway doses.
The assessment of radiation doses shall be performed in ac:ordance with the OFFSITE DOSE CALCULATION MANUAL l
(00CP).
If the dose to the maximum exposed MEMBER OF THE PUBLIC due to the radioactive l
, liquid and gasecus affluents from the st& tion during the previous calendar l
year excer.ds twiec the limits of Specification: 3.II.1.2a, 3.11.1.2.b.
l 3.11.2.2.a. 3.11.2.2.b. 3.11.2.3.a. or 3.11.2.3.b. the dose assessment shall include the contribution from direct radiation.
The dose to the maximum oxcosed HEMBER OF THF. PUBLiC shall show conformance with 40 CFR Part 190.
Environmontal Radiation Protection Standards for Nuclear Power Operations.
The Radioictive Effluent Release Reports shall include a list of unplanned releases as required to be reported in Section 50.73 to 10 CFR Part 50 from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.
The Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) and to the OFFSITE DOSE CALCULATION MANUAL (00CM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Specification 3.12.2.
- A single submittal may be made for a multiple unit station.
The submittal should combine those sections that are connon to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.
NORTH ANNA - UNIT -
6-20 Amendment No. 4,63
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