ML20077L401
| ML20077L401 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 12/29/1994 |
| From: | Mckee P Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20077L406 | List: |
| References | |
| NUDOCS 9501110331 | |
| Download: ML20077L401 (26) | |
Text
e
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)h UNITED STATES j
j NUCLEAR REGULATORY CpMMISSION WASHINGTON, D.C. 20066 0001 s.,...../
NORTHEAST NUCLEAR ENERGY COMPANY. ET AL.
DOCKET NO. 50-423 MILLSTONE NUCLEAR POWER STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 99 License No. NPF-49 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee), dated July 22, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The faci'lity will operate in conformity 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 (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
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 amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
l 9501110331 941229 DR ADOCK 05000423 PDR i
v a.
- l l
l 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. NPF-49 is hereby amended to read as follows:
l (2)
Iggbnical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 99
, and the Environmental Protection i
Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
l 3.
This license amendment is effective as of the date of its issuance, to be implemented within 30 days of issuance.
l FOR THE NUCLEAR REGULATORY COMMISSION
(
i Allo 4v Phillip F. McKee, Director 4D Project Directorate I-4 Division of Reactor Projects - I/II l
Office of-Nuclear Reactor Regulation i
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 29, 1994 I
j i
l
.. =.
e ATTACHMENT TO LICENSE AMENDMENT NO. 99 t
FACILITY OPERATING LICENSE NO. NPF-49 DOCKET NO. 50-423 i
Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
t Remove Insert iv iv 3/4 1-8 3/4 1-8 3/4 1-8a 3/4 1-9 3/4 1-9 3/4 2-5 3/4 2-5 3/4 2-6 3/4 2-6 3/4 2-7 3/4 2-7 3/4 2-8 3/4 2-8 3/4 2-9 3/4 2-9 i
3/4 2-10 3/4 2-10 3/4 2-11 3/4 2-11 3/4 2-12 3/4 2-12 3/4 2-13 3/4 2-13 3/4 2-14 3/4 2-14 3/4 2-15 3/4 2-15 3/4 2-16 3/4 2-16 3/4 2-17 3/4 2-17 1
3/4 2-18 3/4 2-18 3/4 4-6 3/4 4-6 3/4 4-6a 3/4 9-1 3/4 9-1 B 3/4 1-1 B 3/4 1-1 B 3/4 4-1 8 3/4 4-1 i
I k
s
l l
I!EIX LIMITING COMITIONS FOR OPERATION AM SURVEILLANCE REQUIREMENTS SECTION EAGE 3/4.0 APPLICABILITY......................... 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL Shutdown Margin - MODES 1 AND 2.............. 3/4 1-1 Shutdown Margin - MODES 3, 4, AND 5 LOOPS FILLED 3/4 1-3 FIGURE 3.1-1 REQUIRED SHUTDOWN MARGIN FOR MODE 3 WITH FOUR LOOPS IN OPERATION 3/4 1-4 FIGURE 3.1-2 REQUIRED SHUTDOWN MARGIN FOR MODE 3 WITH THREE LOOPS IN OPERATION............. 3/4 1-5 FIGURE 3.1-3 REQUIRED SHUTDOWN MARGIN FOR MODE 4.......... 3/4 1-6 FIGURE 3.1-4 REQUIRED SHUTDOWN MARGIN FOR MODE 5 WITH RCS LOOPS FILLED................. 3/4 1-7 Shutdown Margin - Cold Shutdown -
Loops Not Filled 3/4 1-8 FIGURE 3.1-5 REQUIRED SHUTDOWN MARGIN FOR MODE 5 WITH RCS LOOPS NOT FILLED 3/4 1-9 l
Moderator Temperature Coefficient............. 3/4 1-10 Minimum Temperature for Criticality............ 3/4 1-12 3/4.1.2 B0 RATION SYSTEMS Flow Path - Shutdown 3/4 1-13 Flow Paths - Operating 3/4 1-14 Charging Pump - Shutdown 3/4 1-15 Charging Pumps - Operating 3/4 1-16 Borated Water Source - Shutdown.............. 3/4 1-17 Borated Water Sources - Operating............. 3/4 1-18 3/4.1.3 MOVABLE CONTROL ASSEMBLIES Group Height 3/4 1-20 TABLE 3.1-1 ACCIDENT ANALYSES REQUIRING REEVALUATION IN THE EVENT OF AN INOPERABLE FULL-LENGTH R0D 3/4 1-22 Position Indication Systems - Operating.......... 3/41-23 MILLSTONE - UNIT 3 iv Amendment No. pp, pp, 99 0206
c.
REACTIVITY CONTROL SYSTENS SHUTD0WN MARGIN - COLD SHUTDOWN - LOOPS NOT FILLED LIMITING COM ITION FOR OPERATION 3.1.1.2 The SHUTDOWN MARGIN shall be greater than or equal to a) the limits.shown in Figure 3.1-5 or b) the limits shown in Figure 3.1-4, with the chemical and volume control system (CVCS) aligned to preclude reactor coolant system boron concentration reduction.
APPLICABILITY: MODE 5 LOOPS NOT FILLED ACTION:
a.
With the SHUTDOWN MARGIN less than the above, immediately initiate and I
continue boration at greater than or equal to 33 gpm of a soluti containing greater than or equal to 6300 ppm boron or equivalent -.
the required SHUTDOWN MARGIN is restored.
b.
With the CVCS dilution flow paths not closed and secured in position in accordance with Specification 3.1.1.2(b), immediately close and secure the paths or meet the limits shown in Figure 3.1-5.
SURVEILLANCE REQUIRENENTS 4.1.1.2.1 The SHUTDOWN MARGIN shall be determined to be greater than or equal to the above:
a.
Within 1 bour after detection of an inoperable control rod (s) and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter while the rod (s) is inoperable.
If the inoperable control rod is immovable or untrippable, the SHUTDOWW MARGIN shall be verified acceptable with an increased allowance for the withdrawn worth of the immovable or untrippable control rod (s); and b.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by consideration of the following factors:
1)
Reactor Coolant System boron concentration, 2)
Control rod position, 3)
Reactor Coolant System average temperature, 4)
Fuel burnup based on gross thermal energy generation, NILLSTONE - UNIT 3 3/4 1-8 Amendment No. pp 99 0200
REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 5)
Xenon concentration, and 6)
Samarium concentration.
i 4.1.1.2.2 At least once per 31 days the following valves shall be verified closed and locked. The valves may be opened on an intermittent basis under administrative controls except as noted.
Valve Number Valve Function Valve Position 1.
V304(Z-)
Primary Grade Water Closed to CVCS 2.
V120(Z-)
Moderating Hx Outlet Closed 3.
V147(Z-)
BTRS Outlet Closed 4.
V797(Z-)
Failed Fuel Monitoring Closed Flushing 5.
V100(Z-)
Resin Sluice, CVCS Cation Closed Bed Demineralizer 6.
V571(Z-)
Resin Sluice, CVCS Cation Closed Bed Domineralizer 7.
Vill (Z-)
Resin Sluice, CVCS Cation Closed Bed Demineralizer t
8.
Vil2(Z-)
Resin Sluice, CVCS Cation Closed l
Bed Demineralizer 9.
V98(Z-)/V99(Z-)
Resin Sluice, CVCS Mixed Closed Bed Demineralizer
- 10. V569(Z-)/V570(Z-)
Resin Sluice, CVCS Mixed Closed Bed Domineralizer
- 11. V107(Z-)/V109(Z-)
Resin Slutce, CVCS Mixed Closed Bed Demineralizer
- 12. V108(Z-)/V110(Z-)
Resin Sluice, CVCS Mixed Closed Bed Demineralizer
- 13. V305(Z-)*
Primary Grade Water Closed i
to Charging Pumps
- This valve may not be opened under administrative controls.
g!gLSTONE-UNIT 3 3/4 1-8a Amendment No. 99
- i t
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o 400 800 1200 1600 2000 2m m
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3 RCS CRITICAL BORON CONCDITRATION (ppm)
FIGURE 3.1-5 REQUIRED SHUTDONN MARGIN FOR NODE 5 WITH RCS LOOPS NOT FILLED l
POWER DISTRIBUT101( LIMITS 3/4.2.2 NEAT Fillr HOT CHAISIEL FACTOR - F fZ) 9 FOUR LOOPS OPERATIps LIMITING COMITION FOR OPERATION 3.2.2.1 Fa(Z) shall be limited by the following relationships:
F(Z)s F*"" K(2) for P > 0.5 a
P p*aw F (Z) s K(Z) for P s 0.5 a
0.5 I
Fo* - the Fa limit at RATED THERMAL POWER (RTP) provided in I
the core operating limits report (COLR).
THWAL MR Where:
P, RATED THERMAL POWER,,,4 K(Z) - the normalized Fo(Z) as a function of core height specified in the COLR.
APPLICABILITY: MODE 1.
ACTION:
With Fa(Z) exceeding its limit:
a.
For RAOC operation with Fo(Z) outside the applicable limit specified i
in the COLR, perform one of the following actions:
(1)
Within 15 minutes, control the AFD to within new AFD limits which are determined by reducing the a>plicable AFD limits by 1% AFD for each percent Fo(Z) exceecs its limits.
Within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, reset the AFD alarm setpoints to these modified limits.
I NILLSTONE - UNIT 3 3/4 2-5 Amendment No. pp, pp.99 0210 i
o POWER DISTRIBUTION LINITS LINITING COMITION FOR OPERATION (Continued)
(2)
Reduce THERMAL POWER at least 1% for each 1% Fa(Z) exceeds the limit within 15 minutes and similarly reduce the Power Range Neutron Flux-High Trip Setpoints within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; POWER OPERATION may proceed for up to a total of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; subsequent POWER OPERATION may proceed provided the Overpower AT Trip Setpoints have been reduced at least 1% for each 1%
Fo(Z) exceeds the limit.
(3)
' Verify that the requirements of Specification 4.2.2.1.3 for i
base load operation are satisfied and enter base load operation.
Where it is necessary to calculate the percent that Fo(Z) exceeds the limits for items (1) and (2) above, it shall be calculated as the maximum percent over the core height (Z) that Fo(Z) exceeds its limit by the following expression:
-1 x 100 for P :t 0.5 x K(Z)
-1 x 100 for P < 0. 5 0.5 b.
For base load operation outside the applicable limit specified in the COLR, perform either of the following actions:
(1)
Place the core in an equilibrium condition where the limit in 4.2.2.1.2.C is satisfied, and remeasure F#(Z), or t
i MILLSTONE - UNIT 3 3/4 2-6 Amendment No. 99 0210
s POWER DISTRIBUTION LINITs LINITING COMITION FOR OPERATION (Continued) l (2)
Reduce THERMAL POWER at least 1% for each 1% Fo(Z) exceeds the limit within 15 minutes and similarly reduce the Power Range Neutron Flux-High Trip Setpoints within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; POWER OPERATION may proceed for up to a total of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; subsequent POWER OPERATION may proceed provided the Overpower AT Trip setpoints have been reduced at least 1% for each 1%
Fo(Z) exceeds the limit. The percent that Fo exceeds its limit I
shall be calculated as the maximum percent over the core height (Z) by the following expression:
l
-1 x 100 for P ;t APL"
-=
a c.
Identify and correct the cause of the out-of-limit condition prior to increasing THERMAL POWER above the reduced limit required by ACTION a or b, above; THERMAL POWER may then be increased provided Fo(Z) is demonstrated through incore mapping to be within this limit.
t SURVEILLANCE REQUIRENENTS t
4.2.2.1.1 The provisions of Specification 4.0.4 are not applicable.
4.2.2.1.2 For RAOC operation, Fo(Z) shall be evaluated to determine if Fa(Z) is within its 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 Fo(Z) component of the power distribution map by 3% to account for manufacturing tolerances and further increasing the value by 5% to account for measurement uncertainties.
Verify the requirements of Specification 3.2.2.1 are satisfied.
l NILLSTONE - UNIT 3 3/4 2-7 Amendment No. JP, JP, 99 0210
2
. POWER DISTRI8t1 TION LINITS SURVEILLANCE REQUIRENENTS (Continued) c.
Satisfying the following relationship:
Ff(Z) s F*"" x K(Z) for P > 0.5 PxW(Z) i i
Ff(Z) $ F*"" x K(Z) for P s 0.5 l
W(Z) x 0.5 where Fj(Z) is the measured Fa(Z) increased by the allowances for manufacturing tolerances and measurement uncertainty, FE" is the -
limit, K(Z) is the normalized Fo(Z) as a function of core heigL.
is the relative THERMAL POWER, and W(Z) is the cycle-dependent function that accounts for power distribution transients encountered during normal operation. FE", K(Z), and W(Z) are specified in the CORE OPERATING LIMITS REPORT as per Specification 6.9.1.6.
d.
Measuring F"o(Z) according to the following schedule:
(1) Upon achieving equilibrium conditions after exceeding by 10% or more of RATED THERMAL POWER, the THERMAL POWER at which Fo(Z) was last determined,* or i
(2) At least once per 31 Effective Full Power Days, whichever occurs first.
e.
With the maximum value of Ff(Z)
K(Z) over the core height (Z) increasing since the previous determination of F5(Z), either of the following actions shall be taken:
(1) F#(Z) shall be increased by 2% over that specified in Specifi-cation 4.2.2.1.2c, or During power escalation at the beginning of each cycle, power level may be increased until a power level for extended operation has been achieved and i
power distribution map outlined.
NILLSTONE - UNIT 3 3/4 2-8 Amendment No. pp, pp,99 0210 1
O
.c POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIRENENTS (Continued)
(2) F5(Z) shall be measured at least once per 7 Effective Full Power Days until two successive maps indicate that the maximum value of Fy(Z) '
K(Z) over the core height (Z) is not increasing.
f.
The limits specified in Specifications 4.2.2.1.2c and 4.2.2.1.2e above are not applicable in the following core plane regions:
(1) Lower core region from 0% to 15%, inclusive.
(2) Upper core region from 85% to 100%, inclusive.
4.2.2.1.3 Base load operation is permitted at powers above APL"" if the following conditions are satisfied:
a.
Prior to entering base load operation, maintain THERMAL POWER above APL"" and less than or equal to that allowed by Specifica-tion 4.2.2.1.2 for at least the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Maintain base load operation surveillance (AFD within the target band limit about the l
target flux difference of Specification 3.2.1.1) during this time r
period. Base load operation is then permitted providing THERMAL POWER is maintained between APL"" and APL" or between APL" and 100%
(whichever is most limiting) and Fo surveillance is maintained pursuant to Specification 4.7.2.1.4.
APL" is defined as the minimum value of:
F*" x K(Z)
APL" =
x 100%
Ff(Z) x W(Z),
over the core height (Z) where:
Fs(Z) is the measured Fa(Z) increased by the allowances for manufacturing tolerances and mea-surement uncertainty.
The Fa limit is Fa".
W(Z)n is the cycle-dependent function that accounts for limited power d{'stribution transient encountered during base load operation.
Fa ', K(Z), and W(Z)n are specified in the COLR as per Specification 6.9.1.6.
MILLSTOME - LHIT 3 3/4 2-9
. amendment No. pp, pp.99 l
0310
e i
i'.
POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) b.
Durgg base load operation, if tha THERMAL POWER is decreased below APL then the conditions of 4.2.2.1.3.a shall be satisfied before reentering base load operation.
4.2.2.1.4 During base load operation Fo(Z) shall be evaluated to determine if Fo(Z)iswithinitslimitby:
i a.
Using the movable incore detectors to obtain a power distribution map at any THERMAL POWER above APL"".
b.
Increasing the measured Fo(Z) component of the power distribution map by -3% to account for manufacturing tolerances and further increasing the value by 5% to account for measurement uncertainties.
Verify the requirements of Specification 3.2.2.1 are satisfied.
c.
Satisfying the following relationship:
t i
Ff(Z) $ F*"" x K(Z) for P > APl*
P x W(Z),
whatre: Fs(Z) is the' measured Fo(Z).
Fo"" is the Fa limit, the l
normalized Fo(Z) as a function of core height.
P is the relative THERMAL POWER. W(Z) is the cycle-dependent function that accounts for limited power distributi n 4, transients l
encountered during base load operation.
Fa K(Z), and W(Z)a are specified in the COLR as per Specification 6.9.1.6.
]
d.
Measuring F#(Z) in conjunction with target flux difference determi-nation according to the following schedule:
j (1)
Prior to entering base load operation after satisfying Sec-tion 4.2.2.1.3 unless a full core flux map has been taken in the previous 31 EFPD with the relative thermal power having been maintained above APL"D for the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to mapping, and (2) At least once per 31 Effective Full Power Days.
MILLSTONE - UNIT 3 3/42-10 Amendment No. pp, pp 99 l
0210
c..-
1 3
1 POWER DISTRIBUTION LIMITS SURVEILUUICE REQUIREMENTS (Continued)
{
e.
With the maximum value of Ff(Z)
K(Z) over the cora height (Z) increasing since the previous determination of F#(Z), either of the following at.?lons shall be taken:
(1) Fy(Z) shall be increased by 2% over that specified in 4.2.2.1.4.c, or (2) F#(Z) shall be measured at least or.ce per 7 Effective Full Power Days until 2 successive maps indicate that the maximum value of Ff(Z)
K(2) over the core height (Z) is not increasing.
f.
The limits specified in 4.2.2.1.4.c and 4.2.2.1.4.e are not applicable in the following core plane regions:
(1) Lower core region 0% to 15%, inclusive.
(2) Upper core region 85% to 100%, inclusive.
4.2.2.1.5 When Fo(Z) is measured for reasons other than meeting the require-ments of Specifications 4.2.2.1.2 or 4.2.2.1.4, an overall measured Fa(Z) shall be obtained from a power distribution map and increased by 3% to account for manufacturing tolerances and further increased by 5% to account for measurement uncertainty.
MILLSTONE - UNIT 3 3/4 2-11 Amendment No. pp, pp. 99 0210
e M R DISTRIBUTION LIMITS l
HEAT FLUI HDT CHAlglEL FACTOR - FJZ1 TIREE LOOPS OPERATING LINITING C0pelTION FOR OPERATION 3.2.2.2 Fa(Z) shall be limited by the following relationships:
y*m.
F(Z)s (K(Z)] for P > 0.375 t
a F (Z) s (K(2)] for P s 0.375 a
0.375 Fo" - The Fo limit at RATED THERMAL POWER (RTP) specified in the CORE OPERATING LIMITS REPORT (COLR).
- #N Where: P = RATED THERMAL POWER, and I
K(Z) - the nomalized Fo(Z) as a function of core height speci-fled in the COLR.
f APPLICABILITY: MODE 1.
ACTION:
With Fo(Z) exceeding its limit:
l a.
For RAOC operation with Fo(Z) outside the applicable limit specified in the COLR,' perform one of the following actions:
(1) Within 15 minutes, control the AFD to within new AFD limits which are determined by reducing the applicable AFD limits. by l
1% AFD for each percent Fa(Z) exceeds its limits.
Within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, reset the AFD alarm setpoints to these modified limits.
(2) Reduce THERMAL POWER at least 1% for each 1% Fa(Z) exceeds the limit within 15 minutes and similarly reduce the Power Range Neutron Flux-High Trip Setpoints within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; POWER i
OPERATION may proceed for up to a total of 'f 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />; subsequent WILLSTONE - UNIT 3 3/4 2-12 Amendment No. pp, pp. 99 ovo l
,y
,.. +
---y,.r--
m
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-w w.
.m l
f POWER DISTRIBUTION LIMITS LIMITING COMITION FOR OPERATION (Continued) l POWER OPERATION may proceed provided the Overpower AT Trip l
Setpoints have been reduced at least 15 for each 15 Fo(Z) exceeds the limit.
The Overpower AT Trip Setpoint reduction shall be performed with the reactor in at least HOT STANDBY.
(3) Verify that the requirements of Specification 4.2.2.1.3 for base i
load operation are satisfied and _ enter base load operation.
l Where it is necessary to calculate the percent that Fo(Z) exceeds the i
limits for items (1) and (2) above, it shall be calculated as the' 1
maximum percent over the core height (Z) that Fo(Z) exceeds its limit i
by the following expression:
t
-1 x 100 for Pa 0.375 x K (Z)
-1 x 100 for P< 0.375 0.375 b.
For base load operation outside the applicable limit specified in the l
COLR, perform either of the following actions:
l (1) Place the core in an equilibrium condition where the. limit in i
4.2.2.2.2.C is satisfied, and remeasure FE(Z), or I
(2) Reduce THERMAL POWER at least 1% for each 1% Fo(Z) exceeds the limit within 15 minutes and similarly reduce-the Power Range Neutron Flux-High Trip Setpoints within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; POWER OPERATION may proceed for up to a total of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; subsequent i
POWER OPERATION may proceed provided the-Overpower AT Trip -
Setpoints have been reduced at least 1% for each 1% Fo(Z) exceeds the limit.
The Overpower AT Trip Setpoint reduction 1
shall be performed with the reactor in at least HOT STANDBY.
The percent that Fo exceeds the limit shall be calculated as the maximum percent over the core height (Z) that Fo(Z) exceeds the limit using the following expression:
NILLSTONI - UNIT 3 3/4 2-13 Amendment No. 99 one
w POWER DISTRIBUTION LINITS LIMITING CONDITION FOR OPERATION (Continued)
Fl(Z) x W(Z) A 2.25 y ggg) p c.
Identify and correct the cause of the out-of-limit condition prior to increasing THERMAL POWER above the reduced limit required by ACTION a or b, above; THERMAL POWER may then be increased provided Fo(Z)isdemonstratedthroughincoremappingtobewithinitslimit.
SURVEILLANCE REQUIRENENTS 4.2.2.2.1 The provisions of Specification 4.0.4 are not applicable.
4.2.2.2.2 For RAOC operation, Fo(Z) shall be evaluated to determine if Fo(Z) is within its 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 Fo(Z) component of the power distribution map by 3% to account for manufacturing tolerances and further increasing the value by 5% to account for measurement uncertainties. Verify the requirements of Specification 3.2.2.2 are satisfied.
c.
Satisfy the following relationship:
Ff(Z) $ F*"" x K(Z) for P > 0.375 P x !(Z)
F*"" x K(Z)
Fy(Z) s #(2) x 0.375 for P S 0.375 where F#(Z) is the measured Fo(Z) increased by the allowances for manufacturing tolerances and measurement uncertainty, FS'" is the Fo limit, K(Z) is the normalized Fo(Z) as a function of core height, P is the relative THERMAL POWER, and W(Z) is the cycle-dependent function that accounts for power distribution transients encountered during normal operation.
FS'", K(Z), and W(Z) are specified in the COLR as per Specification 6.9.1.6.
NILLSTONE - UNIT 3 3/4 2-14 Amendment No. JJ, 77,99 l
0210 I
POWER DISTRIBUTION LINITS SURVEILLANCE REQUlf,ENDITS (Continued) d.
Measuring F"a(Z) according to the following schedule:
(1) Upon achieving equilibrium conditions after exceeding by 10% or more of RATED THERMAL POWER, the THERMAL POWER at which Fa(Z) was last determined,* or (2) At least once per 31 Effective Full Power Days, whichever occurs first.
e.
With the maximum value of Ff(Z)
K(Z) over the core height (Z) increasing since the previous determination of F%(Z), either of the following actions shall be taken:
(1) FT(Z) shall be increased by 2% over that specified in Specifica-tion 4.2.2.2.2c, or (2) FT(Z) shall be measured at least once per 7 Effective Full Power Days untti two successive maps indicate that the maximum value of Ff(Z)
K(Z) over the core height (Z) is not increasing, f.
The limits specified in Specifications 4.2.2.2.2c and 4.2.2.2.2e are not applicable in the following core plane regions:
(1) Lower core region from 0% to 15%, inclusive.
(2) Upper core region from 85% to 100%, inclusive.
l l
- During power escalation at the beginning of each cycle, the power level may be increased until a power level for extended operation has been achieved and power distribution map obtained.
gIgLSTONE-UNIT 3 3/4 2-15 Amendment No. 77, pp, JJ, 99 l
POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIRENENTS (Continued) 4.2.2.2.3 Base load operation is permitted at powers above APL"" if the following conditions are satisfied:
a.
Prior to entering base load operation, maintain THERMAL POWER above APL""
and less than or equal to that allowed by Specification 4.2.2.2.2 for at least the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Maintain base load operation surveillance (AFD within the target band limit about the target flux difference of Specification 3.2.1.2) during this time period.
Base load operation is then provi THERMAL POWER is maintained between APL"" and APL"permittedor between APL"ging and100%(whicheveris most limiting) and Fo surveillance is maintained pursuant to Specification 4.2.2.2.4.
APL" is defined as the minimum value of:
F*" x K(Z)
APL" =
x 100%
F;(Z) x W(Z),
over the core height (Z) where: F5(Z) is the measured F (Z) increased o
by the allowances for manufacturin tolerances and measurement uncertainty.
The Fo limit is FS". g W(Z)n is the cycle-dependent function that accounts for limited power distribution transient encountered during base load operation.
FE", K(Z), and W(Z) are specified in the COLR as per Specification 6.9.1.6.
b.
APL""g base load operation, if the THERMAL POWER is decreased below Durin then the conditions of 4.2.2.2.3.a shall be satisfied before reentering base load operation.
4.2.2.2.4 During base load operation Fo(Z) shall be evaluated to determine if Fo(Z) is within its limit by:
a.
Using the movable incore detectors to obtain a power distribution map at any THERMAL POWER above APL".
b.
Increasing the measured Fo(Z) component of the power distribution map by 3% to account for manufacturing tolerances and further increasing the value by 5% to account for measurement uncertainties. Verify the requirements of Specification 3.2.2.2 are satisfied.
I i
NILLSTONE - UNIT 3 3/4 2-16 Amendment No. 77 JP, JP, 99
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0210 1
s POWER DISTRIBUTION LINITS SURVEILLANCE REQUIRENENTS (Continued) j c.
Satisfying the following relationship:
Ff(Z) S 'F*"" x K(Z) for P > APL" P x W(Z),
where:
F%(Z) is the measured Fo(Z).
The Fo" is the Fo limit, the nomalized Fa(Z) as a function o7 core height.
P is the relative THERMAL POWER.
W(Z)a is the cycle-dependent function that accounts for limited pow r distribution transients encountered during base load g
operation.
Fa, K(Z), and W(Z)n are specified in the COLR as per Specification 6.g.l.6.
d.
Measuring FY(Z) in con, junction with target flux difference determina-tion according to the following schedule:
I (1) Prior to entering base load operation after satisfying Sec-tion 4.2.2.2.3, unless a full core flux map has been taken in the previous 31 Effective Full Power Days with the relative THERMAL POWER having been maintained above APL" for the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to mapping, and (2) At least once per 31 Effective Full Power Days.
e.
With the maximum value of Ff(z)
K(z) overthecoreheight(Z)increasingsincethepreviousdetermination of F5(Z), either of the following actions shall be taken:
(1) F5(Z) shall be increased by 2 percent over that specified in 4.2.2.2.4.c, or NILLSTONE - UNIT 3 3/4 2-17 Amendment No. 77, 5, M : 99 l
0210
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POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued)
(2) F"atZ) shall be measured at least once per 7 Effective Full Power Days until 2 successive maps indicate that the maximum value of 1
ff(Z)
K(2) over the core height (Z) is not increasing.
f.
The limits specified in 4.2.2.2.4.c and 4.2.2.2.4.e are not applicable in the following core plane regions:
(1) Lower core region 0% to 15%, inclusive.
l (2) Upper core region 85% to 100%, inclusive.
l 4.2.2.2.5 When Fa(Z) is measured for reasons other than meeting the require :
[
ments of Specifications 4.2.2.2.2 or 4.2.2.2.4, an overall measured Fa(Z) shall l
l be obtained from a power distribution map and increased by 3% to account for manufacturing tolerances and further increased by 5% to account for measurement uncertainty.
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NILLSTONE - UNIT 3 3/4 2-18 Amendment No. E, M. 5, 99 l
0210 f
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REACTOR C00LAlfT SYSTEN COLD SitfTD0lAl - LOOPS 110T FILLED l
LIMITING COWITION FOR OPERATION l
'3.4.1.4.2 Two residual heat removal (RHR) loops shall be OPERABLE
- and at least one RHR loop shall be in operation.**
l APPLICABILITY: N00E 5 with less than two reactor coolant loops filled.
ACTION:
a.
With less than the above required RHR loops OPERABLE, immediately initiate corrective action to return the required RHR loops to OPERABLE status as soon as possible.
b.
With no RHR loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required RHR l
loop to operation.
l l
SURVEILLANCE REQUIREMENTS j
4.4.1.4.2.1 The required RHR loops shall be demonstrated OPERABLE pursuant h
to Specification 4.0.5.
4.4.1.4.2.2 At least one RHR loop shall be detemined to be in operation l
and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
i i
j i
- 0ne RHR loop may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing provided the other RHR loop is OPERABLE and in operation.
- The RHR pump may be deenergized for up to I hour provided:
(1) no opera-tions are permitted that would cause dilution of the Reactor Coolant System boron concentration, and (2) core outlet temperature is maintained at least 10*F below saturation temperature.
MILLSTONE - UNIT 3 3/4 4-6 Amendment No. pp, 99 0215 9
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m
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3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION LINITING COM ITION FOR OPERATION 3.9.1.1 The boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained uniform and sufficient to ensure that the more restrictive of the following reactivity conditions is met; either:
a.
A 4 of 0.95 or less, or b.
A boron concentration of greater than or equal to 2600 ppa.
Additionally, the CVCS valves of Specification 4.1.1.2.2 shall be closed and l
secured in position.
APPLICABILITY: NODE 6.*
ACTION:
a.
With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes and initiate and continue boration at greater than or equal to 33 gpm of a solution containing greater than or equal to 6300 ppm boron or its equivalent untti 4 is reduced to less than or equal to 0.95 or the boron concentration is restored to greater than or equal to 2600 ppe, whichever is the more restrictive.
b.
With any of the CVCS valves of Specification 4.1.1.2.2 not closed **
l and secured in position, immediately close and secure the valves.
SURVEILLANCE REQUIREMENTS 4.9.1.1.1 The more restrictive of the above two reactivity conditions shall be detemined prior to:
a.
Removing or unbolting the reactor vessel head, and b.
Withdrawal of any full-length control rod in excess of 3 feet from its fully inserted position within the reactor vessel.
4.9.1.1.2 The boron concentration of the Reactor Coolant System and the refueling canal shall be deterained by chemical analysis at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
4.9.1.1.3 The CVCS valves of Specification 4.1.1.2.2 shall be verified closed l
and locked at least once per 31 days.
- The reactor shall be maintained in NDDE 6 whenever fuel is in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.
- Except those opened under administrative control.
NILLSTONE - UNIT 3 3/4 9-1 Amendment No. pp, pp,99 0219
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l 3/4.1 REACTIVITY C0ER0L SYSTEMS l
BASES f
3/4.1.1 B0 RATION CONTROL
[
3/4.1.1.1 and 3/4.1.1.2 SHUTDOWN MARGIN i
A sufficient SHUTDOWN MARGIN ensures that:
(1) the reactor can be made subcritical from all operating conditions, (2) the reactivity transients asso-ciated with postulated accident conditions are controllable within acceptable limits, and (3) the reactor will be maintained sufficiently subcritical to preclude inadvertent criticality in the shutdown condition.
SHUTDOWN MARGIN requirements vary throughout core life as a function of fuel depletion, RCS boron concentration, and RCS T.
In MODES I and 2, the most restrictive condition occurs at E0L with T, at no load operating temperature, and is associated with a postulated steam line break accident and resulting uncontrolled RCS cooldown.
In the analysis of this accident, a minimus SHUTDOC MARGIN of 1.3% AK/K is required to control the reactivity transient.
Accordingly, the SHUTDOWN MARGIN requirement is based upon this l
limiting condition and is consistent with FSAR safety analysis assumptions.
In MODES 3, 4 and 5, the most restrictive condition occurs at B0L, associated with a boron dilution accident. In the analysis of this accident, a minimum SHUTDOWN MARGIN as defined in Specification 3/4.1.1.2 is required to allow the operator 15 minutes from the initiation of the Shutdown Margin Monitor alarm to total loss of SHUTDOWN MARGIN.
Accordingly, the SHUTDOWN MARGIN requirement is based upon this limiting requirement and is consistent with the accident analysis assumption. The required SHUTDOWN MARGIN is plotted as a function of RCS critical boron concentration.
The locking closed of the required valves in MODE 5 (with the loops not filled) will preclude the possibility of uncontrolled boron dilution of the l
Reactor Coolant System by preventing flow of unborated water to the RCS.
l 3/4.1.1.3 MODERATOR TEMPERATURE COEFFICIENT The limitations on moderator temperature coefficient (MTC) are provided to ensure that the value of this coefficient remains within the limiting l
condition assumed in the FSAR accident and transient analyses, j
The MTC values of this specification are applicable to a specific set of i
plant conditions; accordingly, verification of MTC values at conditions other than those explicitly stated will require extrapolation to those conditions in l
order to permit an accurate comparison.
The most negative MTC, value equivalent to the most positive moderator l
density coefficient (MDC), was obtained by incrementally correcting the E used in the FSAR analyses to nominal operating conditions.
NILLSTONE - UNIT 3 5 3/4 1-1 Amendment No. 77, pp nm 99
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3/4.4 REACTOR C0OLANT SYSTEN BASES 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION
[
The plant is designed to operate in MODES. I and 2 with three or four j
reactor coolant loops in operation and maintain DN8R greater than the design i
limit during all normal operations and anticipated transients. With less than i
the required reactor coolant loops in operation this specification requires that the plant be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
j In MODE 3, three reactor coolant loops, and in Mode 4, two reactor coolant loops provide sufficient heat removal capability for removing core decay heat even in the event of a bank withdrawal accident; however, a single i
reactor coolant loop provides sufficient heat removal capacity if a bank withdrawal accident can be prevented, i.e., by opening the Reactor Trip System breakers.
In MODE 4, and in MODE 5 with reactor coolant loops filled, a single reactor coolant loop or RHR loop provides sufficient heat removal car, ability for removing decay heat; but single failure considerations requir'.e that at.
least two loops (either RHR or RCS) be OPERABLE.
In MODE 5 with reactor coolant loops not filled, a sirgle RHR loop provides sufficient heat removal capability for removing dr, cay heat; but single failure considerations, and the unavailability of the steam generators as a heat removing component, require that at least two RHR loops be OPERABLE.
The operation of one reactor coolant pump (RCP) or one RHR pump provides adequate flow to ensure mixing, prevent stratification and produce gradual reactivity changes during boron concentration reductions in the Reactor l
Coolant System.
The reactivity change rate associated with boron reduction l
will, therefore, be within the capability of operator recognition and control.
1 The restrictions on starting an RCP with one or more RCS cold legs less than or equal to 350*F are provided to prevent RCS pressure transients, caused by energy additions from the Secondary Coolant System, which could exceed the i
limits of Appendix G to 10 CFR Part 50.
The RCS will be protected against j
overpressure transients and will not exceed the limits of Appendix G by j
either: (1) restricting the water volume in the pressurizer and thereby providing a volume for the reactor coolant to expand into, or (2) by restricting starting of the RCPs to when the secondary water temperature of each steam generator is less than 50'F above each of the RCS cold leg temperatures.
MILLSTONE - UNIT 3 B 3/4 4-1 Amendment No. 7, pp, 99 0210 i