ML20248E544
| ML20248E544 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 03/28/1989 |
| From: | Black S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20248E546 | List: |
| References | |
| NUDOCS 8904120277 | |
| Download: ML20248E544 (19) | |
Text
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d UNITED STATES g.
NUCLEAR REGULATORY COMMISSION -
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WASHINGTON, D. C. 20655
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_ TENNESSEE VALLEY AUTHORITY 00CKET'NO. 50-327
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1 SEQUOYAH NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE-
' Amendment No. 108 1
License No. DPR-77 1.
The Nuclear Regulatory Comission (the Comission)' has found that:
A.
The application for amendment by Tennessee Valley Authority- (the licensee) dated January 31 and March 9, 1989, complies with the.
standards and requirements of the Atomic Energy Act of 1954, as as amended (the act) and the Comission's rules and regulations set -
forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of.the Commission; i
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 CFL Part 51 j
of the Commission's regulations and all' applicable requirements have 1
been satisfied.
e 8904120277 890328 ADOCK0500g7 PDR P
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' 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. DPR-77 is hereby amended to read as follows:
s (2) Technical Specifications The Technical Specifications contained in' Appendices A'and B, as revised through Amendment No.108, are hereby incorporated in the license. The licensee shall operate the facility in accordance with
]
the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
f FOR THE NUCLEAR REGULATORY COMMISSION datn<4_.
Suzann Black, Assistant Director for. Projects TVA Projects Division Office of Nuclear Reacter Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: March 28, 1989 1
i i
ATTACHMENT TO LICENSE AMENDMENT NO. 108 FACILITY OPERATING LICENSE NO. DPR-77 DOCKET N0. 50-327 Revise the Appendix'A Technical Specifications by removing the pages i
identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change. Overleaf pages* are provided to i
maintain document completeness.
REMOVE INSERT 3/4 1-19 3/4 1-19 3/4 1-20 3/4 1-20 t
3/4 1 3/4 1-21*
3/4 1-22 3/4 1-22 3/4 1-23 3/4 1-23 83/4 1-3 B3/4 1-3*
B3/4 1-4 83/4 1-4
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RdACTIVITY CONTROL SYSTEMS
-ROD OR0P TIME LIMITING CONDITION FOR'0PERATION 3.1.3.4 The individual full length (shutdown and control) rod drop time from l
g the fully withdrawn position shall be less than or equal to 2.2 seconds from u
beginning of decay'of stationary gripper coil voltage to dashpot entry with:
a.
T greater than or equal to 541 F, and avg b.
All reactor coolant pumps operating.
APPLICABILITY:
MODES 1 and 2 ACTION:
l a.
With the drop time of any full length rod determined to exceed the above limit, restore the rod drop time to within the above limit l
prior to proceeding to MODE 1 or 2.
b.
With the rod drop times within limits but determined with 3 reactor coolant pumps operating, operation may proceed provided THERMAL POWER is restricted to less than or equal to 71% of RATED THERMAL POWER 1
SURVEILLANCE REQUIREMENTS l
4.1.3.4 The rod drop time of full length rods shall be demonstrated through l
measurement prior to reactor criticality:
For all rods following each removal of the reactor vessel head, a.
l b.
For specifically affected individual rods following any main-tenance 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.
- Fully withdrawn shall be the condition where shutdown and control banks are at a position within the interval of > 222 and < 231 steps withdrawn, inclusive.
l SEQUOYAH - UNIT 1 3/4 1-19 Amendment No. 108 a
P i
n.
RfACTIVITY CONTROL SYSTEMS l
SHUTD0WN R00 INSERTION LIMIT LIMITING CONDITION FOR OPERATION 3.1. 3. 5 All shutdown rods shall be fully withdrawn.**
-APPLICABILITY:
MODES 1* and 2*#
l ACTION:
I With a maximum of one shutdown rod not fully withdrawn, except for surveillance testing pursuant to Specification 4.1.3.1.2, within one hour ~ either:
l
'a.
Fully withdraw the rod, or b.
Declare the rod to be inoperable and apply Specification 3.1.3.1.
l l
l l
l SURVEILLANCE REQUIREMENTS
]
4.1.3.5 Each shutdown rod shall be determined to be fully withdrawn:
Within 15 minutes prior to withdrawal of any rods in control a.
banks A, B, C or 0 during an approach to reactor criticality, j
and b.
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.
- See Special Test Exceptions 3.10.2 and 3.10.3.
- With Keff. greater than or equal to 1.0.
- Fully withdrawn shall be the condition where shutdown and control banks are at a position within the interval of > 222 and 1231 steps withdrawn, inclusive.
l SEQUOYAH.- UNIT 1 3/4 1-20 Amendment No. 108 l
l
_________m
C.,
REACTIVITY CONTROL SYSTEMS CONTROL ROD INSERTION LIMITS LIMITING CONDITION FOR OPERATION 3.1.3.6 The control banks shall be 1.imited in physical insertion as shown in Figure 3.1-1.
APPLICABILITY:
MODES 1* and 2*#.
ACTION:
With the control banks inserted beyond the above insertion limits, except for surveillance testing pursuant to Specification 4.1.3.1.2, either:
a.
Restore the control banks to within the limits within two hours, or
' b.
Peduce THERMAL POWER within two hours to less than or equal to that fraction of RATED THERMAL POWER which is allowed by the group position using the above figures, or c.
Be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.1.3.6 The position of each control bank shall be determined to be within
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the insertion limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals when the Rod Insertion Limit Monitor is inoperable, then verify the individual rod positions at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
^See Special Test Exceptions 3.10.2 and 3.10.3.
- With Keff greater than or equal to 1.0.
SEQUOYAH - UNIT 1 3/4 1-21 Amendment No. 41
N REACTIVITY CONTROL SYSTEMS (Fully Withdrawn)*
(0.05,222[
(0.61. 2223 227
@ SANK 8:
3 Ito,210l'
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200
,f' (1.'0,182)j
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150 "I
8ANK C.
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8ANK D-Y5Eh
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(0.19, 0); r 0
0 0.2 0,4 0.6 0.8 1.0
' (Fully PRACTION OF RATED THERMAL POWER inserted)
FIGURE 3.1-1 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER FOUR LOOP OPERATION QSee page 3/4 1-23 SEQUOYAH - UNIT 2 3/4 1-22 Amendment No. 98
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RBACTIVITY CONTROL SYSTEMS I
FIGURE 3.1-1 NOTATION l
(
Fully withdrawn shall be the condition where shutdown and control banks are
(
at a position within the interval of > 222 and < 231 steps withdrawn,
)
inclusive.
j There are no rod insertion limits when the shutdown and control banks are at a position within the interval > 222 and < 231 steps withdrawn, inclusive.
l The fully withdrawn position shill be specified in a reload safety evaluation for each cycle of operation and, once specified, shall not be changed unless such a change is specifically evaluated.
1 1
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1 1
SEQUOYAH - UNIT 1 3/4 1-23 Amendment No. 41,108
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R$ ACTIVITY CONTROL SYSTEMS BASES 5408 gallons of 20,000 ppm borated water from the boric acid storage tanks or 64,160 gallons of 2000 ppm borated water from the refueling water storage tank.
With the RCS temperature below 200 F, one 1.njection system is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the additional restrictions prohibiting CORE ALTERATIONS;and positive reactivity change in the event the single injection system becomes inoperable.
4 I
The boron capability required below 200 F, is sufficient to provide a SHUTOOWN MARGIN of 1% delta k/k after xenon decay and'cooldown from 200 F to 140 F.
This condition requires either~835 gallons of 20,000 ppm borated water from the boric acid storage tanks or 9,690 gallons of 2000 ppm borated water from the refueling water storage. tank.
The contained water volume limits include allowance for water not available l
because of discharge line location and other physical characteristics.
1
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The limits on contained water volume and boron concentration of the RWST also ensure a pH value of between 7.5 and 9.5 for the solution recirculated within contalement after a LOCA.
This pH band minimizes the evolution of.
iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components.
lThe OPERABILITY of one boron injection system during REFUELING ensures that this system is available for reactivity control while in MODE 6.
3/4.1.3 MOVABLE CONTROL ASSEMBLIES The specifications of this section ensure that (1) acceptable power distri-bution limits are maintained, (2) the minimum SHUTDOWN MARGIN is maintained, and (3) limit the potential effects of rod misalignment on associated accident analyses.
OPERABILITY of the control rod position indicators is required to determine control rod positions and thereby ensure compliance with the control
. rod alignment and insertion limits.
l ir l
i I
s SEQUOYAH - UNIT 1 B 3/4 1-3 Revised 08/18/87 Bases Change
c.,
REACTIVITY CONTROL SYSTEMS ~
BASES The ACTION statements which permit limited variations from the basic requirements are accompanied by additional restrictions which ensure that the.
original design criteria are met.
Misalignment of a rod requires measurement.
s of peaking factors and a restriction in THERMAL POWER. These restrictions provide assurance of fuel rod integrity during continued operation.
In addi. tion, those accident analyses affected by a misalignment rod are reevalu-ated to confirm that the results remain valid during future operation.
The maximum rod drop time restriction is consistent with the assumed rod drop time used in the accident analyses.
Measurement with T greater than avg j
or equal to 541 F and with.all reactor coolant pumps operating ensures that the measured drop times will be representative of insertion times experienced i
during a reactor trip at operating conditions, i
Control rod posit' ions and OPERABILITY of the rod position indicators are i
required to be verified on a nominal basis 'of once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with more frequent verifications required if an automatic monitoring channel is inoperable.
j These verification frequencies are adequate for assuring that the applicable
)
LC0's are satisfied.
3/4.1.3.4 R0D DROP TIME and 3/4.1.3.5 SHUTDOWN R00 INSERTION LIMIT Fully withdrawn for shutdown and control rod banks is defined as a-condition where the rod banks are positioned in a range of 222_to 231 steps.
fully withdrawn.
This range is defined to permit axial repositioning of rod banks to mitigate rod wear on internal guide surfaces.
l l
SEQUOYAH - UNIT 1 B 3/4 1-4 Amendment No. 108
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UNITED STATES g
NUCLEAR REGULATORY COMMISSION 7a
'f WASHINGTON, D. C. 20555
%....+/
l TENNESSEE VALLEY AUTHORITY I
DOCKET N0. 50-328 SEQUOYAH NUCLEAR PLANT, UNIT 2 g
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 98 4
License No. DPR-79 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated January 31 and March 9,1989, complies with the
{
standards and requirements of the Atomic Energy Act of 1954, as as amended (the act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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 Commission's regulations; j
D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and i
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
_m_
Q.
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment i
and' paragraph 2.C.(2) of Facility Operating License No. DPR-79 is hereby amended to read as,follows:
(2) Technical Specifications-The Technical Specifications contained in Appendices A and B,-as revised through Amendment No. 98, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of.its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION vv>LL Suzann lack, Assistant Director i
for_ Projects TVA Projects Division l
Office of Nuclear Reactor Regulation Attachntent:
l Changes to the Technical Specifications Date of Issuance:
March 28, 1989
4
.g.
- ATTACHMENT TO LICENSE AMENDMENT N0. 98 FACILITY 0PERATING LICENSE NO. DPR-79 DOCKET NO. 50-328 Revise the Appendix A Technical ~ Specifications by removing the pages identified below and ins'erting the enclosed pages.1The revised pages care identified by_the captioned: amendment number and contain marginal lines-indicating the area of change. Overleaf pages* are provided to maintain document completeness.
REMOVE INSERT
-3/4.1-19 3/4 1-19 3/4 1-20 3/4 1-20 3/4 1-22 3/4 1-22 3/3 1-23 3/4 1-23 B3/4 1-3 B3/4 1-3*
B3/4 1-4 B3/4 1-4 I
1 l
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s.,.
R$ ACTIVITY CONTROL SYSTEMS R00 DROP TIME LIMITING CONDITION FOR OPERATION 3.1. 3. 4 The individual Yull length (shutdown and control) rod drop' time from g
the fully withdrawn position shall be less than or equal to 2.2 seconds from l
beginning of decay of stationary gripper coil voltage to dashpot entry with:
a.
T greater than or equal to 541 F, and avg b.
All reactor coolant pumps operating.
APPLICABILITY: Modes 1 and 2.
. ACTION:
1 a.
With the drop time of any full length rod determined to exceed the above limit, restore the rod drop time to within the above limit prior to proceeding to MODE 1 or 2.
b.
With the rod drop times within limits but determined with 3 reactor coolant pumps operating, operation may proceed provided THERMAL POWER is restricted to less than or equal to 71% of RATED THERMAL POWER.
SURVEILLANCE REQUIREMENTS 4.1.3.4 The rod drop time of full length rods shall be demonstrated through measurement prior to reactor criticality:
For all rods following each removal of the reactor vessel head, a.
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.*
- For cycle 1, this surveillance is to be completed before the next cuoldown or by August 5, 1983, whichever is earlier.
- Fully withdrawn shall be the condition where shutdown and control banks are at a position within the interval of >222 and <231 steps withdrawn, inclusive.
SEQUOYAH - UNIT 2 3/4 1-19 Amendment No. 20, 98
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.1
. REACTIVITY CONTROL ~ SYSTEMS, SHUTDOWN R00 INSERTION LIMIT LIMITING CONDITION FOR OPERATION
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3.1.3.5 All shutdown rods shall be fully withdrawn.**
APPLICABILITY:
Modes 1* and 2*#.
ACTION:
With a maximum of one shutdown rod not fully withdrawn, except'for surveillance testing pursuant.to Specification 4.1.3.1.2, within one hour either:
l 1
a.
Fully withdraw the rod, or b.
Declare the rod to'be inoperable and apply Specification 3.1.3.1.
l
)
SURVEILLANCE REQUIREMENTS 4.1.3.5 Each shutdown rod shall be determined to be fully withdrawn:
Within 15 minutes prior to withdrawal of any rods in control banks a.
A, B, C or D during an approach to reactor criticality, and j
b.
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.
l 1
"See Special Test Exceptions 3.10.2 and 3.10.3.
- With Keff greater than or equal to 1.0
- Fully withdrawn shall be the condition where shutdown and control banks are.
j at a position within the interval of > 222 and < 231 steps withdrawn, inclusive.
l
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SEQUOYAH - UNIT 2 3/4 1-20 Amendment No. 98
y t
(Fully Withdrawn)*
'l 22? __(0.05.'222) p (0.61. 22h gEANK 5::
It0,210)T
_~
200
~
_ - - ~
(1.0,182)j
~-
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150
_--SANK C
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we 100
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SANKD-a
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50
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(0.19, 0);g-0 0.2 0.4 0.8 0.8 -
1.0
, (Fully FRACTION OF RATED THERMAL. POWER insertaall
~
FIGURE 3.1-1 R0D BANK INSERTION LIMITS VERSUS THERMAL. POWER FOUR LOOP OPERATION l
- *See page 3/4 1-23, O
SEQUOYAH'- UNIT 1 3/4 1-22 Amendment No. 108
4 REACTIVITY CONTROL SYSTEMS FIGURE 3.1-1 NOTATION Fully withdrawn shall.be the condition where shutdown and control banks are at a position within the interval of > 222 and < 231 steps withdrawn; inclusive.-
'here are no rod insertion limits when the shutdown and control banks are at a T
1 position within the interval > 222 and < 231 steps withdrawn, inclusive. 'The fully withdrawn position shalT be speciTied in a reload-safety evaluation for each cycle of operation and, once specified, shall not be changed unless.such a change is specifically evaluated.
l I
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SEQUOYAH - UNIT 2 3/4 1-23 Amendment No. 3198 1
1
s.
4
,g REACTIVITY CONTROL SYSTEMS FIGURE 3.1-l' NOTATION Fully withdrawn shall be the condition where shutdown and control banks are at a position within the interval of > 222 and < 231 steps withdrawn, inclusive.
There are no rod insertion-limits when the shutdown and control banks are at a position within the interval > 222 and < 231 steps withdrawn, inclusive..The fully withdrawn position shalT be.speciTied in a reload safety evaluation for each cycle of operation and, once specified, shall not be changed unless'such a change;is.specifically evaluated.
l l
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l SEQUOYAH - UNIT 2 3/4 1-23 Amendment No. 33, 98 l
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- RNACTIVITY CONTROL SYSTEMS BASES BORATION SYSTEMS (Continued) provide a SHUTDOWN MARGIN from expected operating conditions of 1.6% delta k/k after xenon decay and cooldown to 200 F.
The maximum expected boration capability requirement occurs at E0L from full power' equilibrium xenon l
conditions and requires 5408 gallons of 20,000 ppm borated water from the boric acid storage tanks or 64,160 gallons of 2000 ppm borated water from the refueling water storage tank.
With the RCE temperature below 200 F, one injection system is acceptable I
without single 'aflure consideration on the basis of the stable reactivity condition of tne reactor and the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity changes in the event the single injection i
system becomes inoperable.
1 The boron cepability required below 200 F is sufficient to provide a 1
SHUTDOWN MARGIN of 1% delta k/k after y o on decay and cooldown from 200 F to 140 F.
This condition requires either 4.15 gallons of 20,000 ppm borated water from the boric acid storage tanks or 9,690 gallons of 2000 ppm borated water i
from the refueling water storage tank.
The contained water volume limits include allowance for water not 5
available because of discharge line location and other physical characteristics.
The limits on contained water volume and boron concentration of the RWST also ensure a pH value of between 7.5 and 9.5 for the solution recirculated within containment after a LOCA.
This pH band minimizes the evolution of iodine and minimizes the effect of chloride and cost stress corrosion on mechanical systems and components.
The OPERABILITY of one boron injection sy:, tem during REFUELING ensures that this system is available for reactivity control while in MODE 6.
3/4.1.3 M0VABLE CONTROL ASSEMBLIES The specifications of this section ensure that (1) acceptable power distribution limits are maintained, (2) the minimum SHUTDOWN MARGIN is main-tained, and (3) limit the potential effects of rod misalignment on associated accident analyses.
OPERABILITY of the control rod position indicators is required to determine control rod positions and thereby ensure compliance with the control rod alignment and insertion limits.
SEQUOYAH - UNIT 2 B 3/4 1-3 Revised 08/18/87 Bases Change l
4 6,'
1 l
' REACTIVITY CONTROL SYSTEMS BASES l
MOVEABLE CONTROL ASSEMBLIES (Continued)
The ACTION statemen'ts which permit limited variations from the basic requirements are accompanied by additional restrictions which ensure that the original design criteria are mat.
Misalignment of a rod requires measurement of peaking factors and a restriction in THERMAL POWER.
These restrictions provide assurance of fuel rod integrity during continued operation.
In addition, those safety analyses affected by a misaligned rod are reevaluated i
to confirm that the results remain valid during f';ture operation.
The maximum rod drop time restriction is consistent with the assumed. rod drop time used in the safety analyses.
Measurement with.T greater than or avg equal to 541 F and with all reactor coolant pumps operating ensures that the measured drop times will be representative of insertion times experienced during a reactor trip at operating conditions, l
Control rod positions and OPERABILITY of the rod position indicators are required to be verified on a nominal basis of once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with more frequent verifications required if an automatic monitoring channel is inoperable.
These verification frequencies are adequate for assuring that the applicable LCO's are satisfied.
3/4.1.3.4 R00 DROP TIME and 3/4.1.3.5 SHUTDOWN R0D INSERTION LIMIT Fully withdrawn for shutdown and control rod banks is defined as a condition where the rod banks are positioned in a range of 222 to 231 steps fully withdrawn.
This ange is defined to permit axial repositioning of rod banks to mitigate rod wear on internal guide surfaces.
1 SEQUOYAH - UNIT 2 B 3/4 1-4 Amendment No. 98
_. _ _ _ - _ _ _ _ _ _ _