Text

Proposed Tech Specs Re Control Rod Matl & Rod Insertion Limits
	ML20246K227
Person / Time
Site:	Vogtle
Issue date:	08/25/1989
From:	; GEORGIA POWER CO.
To:	;
Shared Package
ML20246K226	List: ELV-00758, Application for Amends to Licenses NPF-68 & NPF-81,revising Rod Insertion Limits of Figure 3.1-3 to Show Fully Withdrawn Position as 222 Steps Instead of 228 Steps; ML20246K227;
References
	NUDOCS 8909050411
	Download: ML20246K227 (7)
	v • d • e

_

/ a 4

ENCLOSURE 3

V0GTLE ELECTRIC GENERATING PLANT l NRC DOCKETS 50-424, 50-425 OPERATING LICENSES NPF-68, NPF-81 REVISION TO TECHNICAL SPECIFICATIONS CONTROL ROD MATERIAL AND R0D INSERTION LIMITS INSTRUCTIONS FOR' INCORPORATION The proposed amendment to the Vogtle Control Rod Material and insertion limits (Appendix A of. Operating Licenses NPF-68 and NPF-81) would be incorporated as follows

Remove Page Insert Page 3/41-19 and 20 3/41-19 and 20 3/41-21* and 22 3/41-21* and 22 3/410-1 and 2* 3/410-1 and 2*

B 3/4 2-1* and 2 B 3/4 2-1* and 2 5-3* and 4 5-3* and 4

Overleaf page containing no change 8909050421 890825 E,DR ADOCK0500g44 E3-1

,:q .

b:

REACTIVITY CONTROL SYSTEMS ROD DROP TIME

' LIMITING CONDITION FOR OPERATION 3.1.3.4 The individual shutdown and control rod drop time from the physical fully withdrawn position shall be less than or equal to 2.2 seconds from beginning of decay of stationary gripper coil voltage to dashpot entry with:

. -a. T avg (TI-0412, TI-0422, TI-0432, TI-0442) greater than or equal to 551 F, and

b. All reactor coolant pumps operating.

APPLICABILITY: MODES 1 and 2.

ACTION:

With the' drop time of any rod determined to exceed the above limit, restore the i rod drop time to within the above -limit prior to proceeding to MODE 1 or 2. '

SURVEILLANCE REQUIREMENTS 4.1.3.4 The rod drop time shall be demonstrated through measurement prior to reactor criticality:

a. For all rods following each removal of the reactor vessel head,

b. For specifically affected individual rods following any maintenance on or modification to the Control Rod Drive System which could affect the drop time of those specific rods, and

c. At least once per 18 months.

L l

V0GTLE UNITS - 1 & 2 3/4 1-19

m. .

-7 n1 ..

. :(

3-REACTIVITY CONTROL SYSTEMS

~ SHUTDOWN ROD INSERTION LIMIT LIMITING CONDITION FOR OPERATION 3.1.3.5 All= shutdown rods'shall be withdrawn to a position greater than

, or equal to 222 steps.

APPLICABILITY: MODES 1* and 2,* #

ACTION:

With'a maximum of one shutdown rod inserted to a position less than 222 steps. . l except for surveillance testing pursuant to Specification 4.1.3.1.2, with

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either:

a. Withdraw the rod to a position greater than or equal to 222 steps, or. l

b. Declare the rod to be inoperable and apply Specification 3.1.3.1.

SURVEILL1NCE REQUIREMENTS 4.1.3.5 Each shutdown rod shall be determined to be withdrawn to a position greater than or equal to 222 steps:

a. . Within 15 minutes prior to withdrawal of any rods in Control Bank A, B, C, or D during an approach to reactor criticality, and

b. At 1 east once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

l

See Special Test Exceptions Specifications 3.10.2 and 3.10.3.

With Kef t greater than or equal to 1.

V0GTLE UNITS - 1 & 2 3/4 1-20

,y *

(26.7,222) (76.7,222) 220 I I ./ I I I If i I 200 E I / BANK B l / l l 180 I I I I I / I I E l

g E /! l / I E q

$ 3ao F I I / l n00.16u E 8 E(0,161) I /l I /E s,,,E I I / BANK C l l[ l 5 E I I / ! ! l / E

$ 12a I I l I/ I I I 1/I E e I I / I I ! / I 5 ,oo l I /I I/ I Ei E I / I / I E 2 / i i /: BANK D l E*II / I I i/ I I I E /

$'E/ E I I I I E/ I i l I E

[ (0,46) l l l [_ / i l l l l l I I I If I I I I I I i I y i i i

i i I 20 , j l ,

ap _ (3P 2 m/ l l l l 0 20 40 60 80 100 RELATIVE POWER (percent)

FIGURE 3.1-3 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER l

l l

V0GTLE UNITS - 1 & 2 3/4 1-22

.e e -

3/4.10 SPECIAL TEST EXCEPTIONS

' 3/4.10.1 - SHUTOOWN MARGIN LIMITIN_G CONDITION-FOR OPERATION 3.10.1 The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 may be L

suspended for measurement of cor. trol rod worth and -SHUTOOWN MARGIN provided reactivity equivalent to at least the highest estimated control rod worth is available for' trip insertion' from OPERABLE control rod (s).

APPLICABILITY: MODE 2.

ACTION:

a. With any control rod not fully inserted and with less than the above reactivity equivalent available for trip insertion, immediately initiate and continue boration at greater than or equal to 30 gpm of a solution containing greater than or equal to 7000 ppm boron or its equivalent until the SHUTOOWN MARGIN required by Specification 3.1.1.1 is restored.

b. With all control rods fully inserted and the reactor subcritical by less than the above reactivity equivalent, immediately initiate and continue boration at greater than or equal to 30 gpm of a solution containing greater than or equal to 7000 ppm boron or its equivalent until the SMUT 00WN MARGIN required by Specification 3.1.1.1 is restored.

SURVEILLANCE RE0VIREMENTS _ _ , ,

I-4.10.1.1 The position of each control rod not fully inserted shall be l determined at least once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

4.10.1.2 Each control rod not fully inserted shall be demonstrated capable of full insertion when tripped from at least the 50% withdrawn position within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to reducing the SHUTDOWN MARGIN to less than the limits of Specification 3.1.1.1.

V06TLE UNITS - 1 & 2 3/4 10-1

g'dL de ' POWER DISTRIBUTION LIMITS

~

' BASES j AXIAL FLUX DIFFERENCE (Continued)

Although it is intended that the plant will be operated with the AFD within the target band required by Specification 3.2.1 about the target flux dif ference, during rapid plant THERMAL POWER reductions, control rod motion

. will cause the AFD to deviate outside of the target band at reduced THERMAL' POWER levels. This deviation will not affect the xenon redistribution suffi-ciently to change the envelope of peaking factors which may be reached on a subsequent return to RATED THERMAL POWER (with the AFD within the target band) provided the time duration of the deviation is limited. Accordingly, a 1-hour penalty deviation limit cumulative during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months is provided for operation outside of the target band but within the limits of Figure 3.2-1 while at THERMAL POWER levels between 50% and 90% of RATED THERMAL POWER. For

. THERMAL POWER levels between 15% and 50% of RATED THERMAL POWER, deviations of the AFD outside of the target band are less significant. The penalty of 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months actual time reflects this reduced significance.

Provisions for monitoring the AFD on an automatic basis are derived from the plant process computer through the AFD Monitor Alarm. The computer deter-mines the 1-minute average of each of the OPERABLE excore detector outputs and provides an alarm message immediately if the AFD for two or more OPERABLE excore channels are outside the target band and the THERMAL POWER is greater than 90% of RATED THERMAL POWER. During operation at THERMAL POWER levels between 50% and 90% and between 15% and 50% RATED THERMAL POWER, the computer outputs an alarm message when the penalty deviation accumulates beyond the limits of-1 hour and 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , respectively.

Figure B 3/4 2-1 shows a typical monthly target band.

3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR pN The limits on heat flux hot channel factor and nuclear enthalpy rise hot channel factor 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 limit.

Each of these is measurable but will normally only be determined periodically as specified in Specifications 4.2.2 and 4.2.3. This periodic surveillance is sufficient to ensure that the limits are maintained provided:

a. Control rods in a single group move together with no individual rod insertion dif fering by more than i 12 steps, indicated, f rom the group demand position;

b. Control rod banks are sequenced with a constant tip-to-tip distance between banks as defined by Figure 3.1-3.

V0GTLE UNITS - 1 & 2 B 3/4 2-2

4: DESIGN FEATURES ~

.1 E '

5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The core shall contain 193 fuel assemblies with each fuel assembly containing 264 fuel rods clad with Zircaloy-4. Each fuel rod shall have a nominal active fuel length of 144 inches The initial core loading shall have a maximum enrichment not to exceed 3.2 weight percent U-235. Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment not to exceed 3.5 weight percent 'U-235.

CONTROL ROD ASSEMBLIES 5.3.2 The core shall contain 53 full-length control rod assemblies. The control rod assemblies shall contain a nominal 142 inches of absorber material.

The nominal absorber composition shall be 95.5% natural halfnium and 4.5%

natural zirconium and/or 80% silver,15% indium, and 5% cadmium. All control l rods.shall be clad with stainless steel.

5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The Reactor Coolant System is designed and shall be maintained:

a. In accordance with the Code requirements specified in Section 5.2 of the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements,

-b. For a pressure of 2485 psig, and

c. For a temperature of 650*F, except for the pressurizer which is 680*F.

VOLUME 5.4.2 The total water and steam volume of the Reacter Coolant System is 12,2'O i 100 cubic feet at a nominal Tavg of 588.5*F.

5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1 and 5.1-2.

V0GTLE UNITS - 1 & 2 5-4 1 - _ _ _ _ . - .____-_-___-_-___________-_a

ML20246K227

Text

Navigation menu

Search