ML17326B530
| ML17326B530 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/15/1989 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17326B531 | List: |
| References | |
| NUDOCS 8902210130 | |
| Download: ML17326B530 (12) | |
Text
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UNITED STATES LEAR REGULATORY COMMISSIO WASHINGTON, D. C. 20555 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-316 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 108 License No. DPR-74 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana Michigan Power Company (the licensee) dated August 15, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, 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 (i) 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; 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 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.
85'022i0i30 8902i5 PDR ADOCK 050003i6 P
PDC I )
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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 Faci lity Operating License No.
DPR-74 is hereby amended to read as follows:
Technical S ecifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No.
IO8, 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 the date of its issuance.
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 15, 1989
~ FOR THE NUCLEAR REGULAT Y COMMISSION C
Theodore quay, Acting Director Project Directorate III-1 Division of Reactor Projects - III, IV, V
& Special Projects
- 7. C'
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO.
FACILITY OPERATING LICENSE NO.
DPR-74 DOCKETS NOS. 50-316 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages ar'e identified by amendment number and contain marginal lines indicating the area of change.
REMOVE 3/4 1-1 3/4 1-2 3/4 1"3 3/4 1"3b 3/4 1-5 3/4 1-6 3/4 3-25 3/4 3-27 B 3/4 1-1 INSERT I
3/4 1-1 3/4 1-2 3/4 1-3 3/4 1-3b 3/4 1-5 3/4 1-6 3/4 3-25 3/4 3"27 B 3/4 1"1
3 4.1 REACTIVITY CONTROL SYSTEMS 3 4.1.1 BORATION CONTROL SHUTDOWN MARGIN - STANDBY STARTUP AND POWER OPERATION M TING ON IT ON R
P RAT 3.1.1.1 The SHUTDOWN MARGIN shall be
> 2.0% hk/k.
APPLICABILITY:
MODES 1, 2*, and 3.
ACTION:
With the SHUTDOWN MARGIN < 2.0% hk/k, immediately initiate and continue boration at
> 10 gpm of 20,000 ppm boric acid solution or equivalen't until the required SHUTDOWN MARGIN is restored.
SURV IL ANC R
U REM N
S 4.1.1.1.1 The SHUTDOWN MARGIN shall be determined to be
> 2.0% hk/k:
a.
b.
Within one hour 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 above required SHUTDOWN MARGIN shall be increased by an amount at least equal to the withdrawn worth of the immovable or untrippable control rod(s).
When in MODES 1 or 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 /> by verifying that control bank withdrawal is within the limits of Specification 3.1.3.6.
c.
When in MODE 2
, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to achieving reactor criticality by verifying that the predicted critical control rod position is within the limits of Specification 3. 1.3.6.
- See Special Test Exception 3.10.1 With K
> 1.0 With K
< 1.0 D.C.
COOK - UNIT 2 3/4 1-1
~mm mo.
gg, 108
REACTIVITY CONTROL SYSTEMS SURVE AN UIR M NTS Continued d.
Prior to initial operation above 5% RATED THERMAL POWER after each fuel loading, by consideration of the factors of e below, with the control banks at the maximum insertion limit of Specification 3.1.3.6.
e.
When in MODE 3, 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, 5.
Xenon concentration, and 6.
Samarium concentration..
- 4. 1. 1. 1.2 The overall core reactivity balance shall be compared to predicted values to demonstrate agreement within t 1% hk/k at least once per 31 Effective Full Power Days (EFPD).
This comparison shall consider at least those factors stated in Specification 4.1.1. l.l.e, above.
The predicted reactivity values shall be adjusted (normalized) to correspond to the actual core conditions prior to exceeding a fuel burnup of 60 Effective Full Power Days after each fuel loading.
- 4. 1. 1.1.3 Prior to blocking ESF Functional Units in accordance with footnotes ¹ and ¹¹ of Table 3.3-3, SHUTDOWN MARGIN shall be determined to be greater than or equal to 2.0% hk/k by consideration of the factors of
- 4. 1.1. 11~ above.
The Reactor Coolant System average temperature used in making this SHUTDOWN MARGIN determination shall be less than or equal to 350'F.
This SHUTDOWN MARGIN shall be maintained at all times when the ESF functions are blocked in MODE 3.
D.
C.
COOK
- UNIT 2 3/4 1-2 mzmmm mo. gg, 108
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1 DO[V<~ GIN -
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T ON 3.1.1.2 The SHUTDOWN MARGIN shall be:
a, In MODE 4:
- 1. Greater than or equal to 2.04 Ak/k when operating with one, or more Reactor Coolant Loops in accordance with Specification 3.4.1.3.
- 2. Greater than the ~alue shown in Figure 3,1-3 when operating with no Reactor Coolant Loops but one, or more Residual Heat Removal Loops in accordance with Specification 3.4.1.3.
b.
In MODE 5:
- 1. Greater than or equal to 1.0% hk/k when operating with one or more Reactor Coolant Loops in accordance with Specification 3.4.1.3.
- 2. Greater than the value shown in Figure 3.1-3 when operating with
,no Reactor Coolant Loops but one or more Residual Heat Removal Loops in accordance with Specification 3.4.1.3.
~CT~OR:
With SHUTDOWN MARGIN less than the above limits, immediately initiate and continue boration at greater than or equal to 10 gpm of 20,000 ppm boric acid solution or equivalent until the required SHUTDOWN lfARGIN is restored.
5 V ILLANCE E UI EME
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4.1.1.2 The SHUTDOWN MARGIN shall be determined to be greater than or equal to the above limits:
a.
Within one hour 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 SHUTDOWN MARGIN shall be increased by an amount at least equal to the withdrawn worth of the immovable or untrippable control rod(s).
D. C.
COOK - UNIT 2 3/4 1-3 AMENDMENT NO.
0~ >>>'08
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CZ lO 6.0 5.0 CO I
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4.0 z
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3.0 0O O
2.0 K
MODE 4
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i~r goo 1.0 ZO Z0 0.0 0 200 400 600 800 1000 1200 BORON CONCENTRATION (PPM) 1400 1600 1800 TQ
~0 lSI
~t CO FIGURE 3.1-3 REQUIRED SHUTDOWN MARGIN
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3.1.1.4 The moderator temperature coefficient (MTC) shall be:
a.
b.
Within the region of acceptable operation in Figure 3.1-2; and
-4 0
Less negative than
-B.S x 10 9c/k/ F for the all rods withdrawn, end of cycle life (EOL),
RATED THERMAL POWER condition.
'" 1 Specification 3.1.1.4.b
- MODES 1, 2 and 3 only¹
~CT~IO With the MTC more positive than the limit of 3.1.1.4.a above:
l.
Establish and maintain control rod withdrawal limits sufficient to restore the MTC to within its limits within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
These withdrawal limits shall be in addition to the insertion limits of Specification 3.1.3.6.
2.
Maintain the control rods within the withdrawal limits established above until subsequent measurement verifies that the MTC has been restored to with'n its limit for the all rods withdrawn condition.
3.
Prepare and submit a Special Repor" to the Commission pursuant to Specification 6.9.2 within 10 days describing the value of the measured MTC, the interim control rod withdrawal limits and the predicted average core burnup necessary for restoring the positive MTC to within its limit for the all rods withdrawn condition.
b.
With the MTC more negative than the limit of 3.1.1.4.b
- above, be in HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- With K ff greater than or equal to 1.0 eff See Special Test Exception 3.10.3 D. C.
COOK - UNIT 2 3/4 1-5 AMENDMENT NO.
27 ~~ P7 ~
'-108
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S REACTIV1TY CONTROL SYSTEMS SURVEI LANCE %EQUIREMENTS 4.1.1.4.1 The MTC shall be determined to be within its limits by confirmatory measurements.
Measured MTC values shall be extrapolated and/or compensated to permit direct comparison with the above limits.
4.1.1.4.2 The MTC shall be determined to be within its limits during each fuel cycle as follows:
a)
The MTC shall be zea ured and compared to the BOL limit of Specification 3.1.1.4.a, above, prior to initial operation above i% of RATED THERMAL POWER, after each fuel loading.
b)
The MTC shall be measured at any THERMAL POWER within 7 EFPD after reaching an equilibrium boron concentration of 300 ppm and the extrapolated MTC value compared to the EOL limit.
In the event this comparison indicates that the MTC will be more negative than the EOL limit, the MTC shall be remeasured at least once per 14 EFPD during the remainder of the fuel cycle and the MTC value compared to the EOL limit.
D. C.
COOK - UNIT 2 3/4 1-6 Amendment No. ~7~i~7~
108
TABLE 3.3-4 Continued ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS Aoo t
FUNCTIONAL UNIT 4.
STEAM LINE ISOLATION TRIP SETPOINT ALMWABLEVALUES a.
Manual b.
Automatic Actuation Logic Not Applicable Not Applicable c.
Containment Pressure High-High
< 2.9 psig Not Applicable Not Applicable
< 3.0 psig d.
Steam Flpw in Two Steam Lines->>
High Coincident with T Low-Lov avg e.
Steam Line Pressure Lov 5 ~
TURBINE TRIP AND FEEDWATER ISOLATION
< A function defined as follows:,
A hp cogrespoei-
'.ing to 1.4? x 10 lbs/hr steam flow between 04 and 20% load and then a hp increasing linearly to a bp6corresponding to 4.02 x 10 lbs/hr at full load.
T
> 541 F.
> 600 psig steam line pressure
< A function defined as follows:
A hp correspond-ing to 1.62 x 10 lbs/hr steam flov betveen 0% and 204 load and then a hp in-creasing linearly to a ap coFesyonding to 4.07 x 10 lbs/hr at full load.
T
> 539 'P.
> 585 psig steam line pressure O
a.
Steaa Generator Water Level
< 6?4 of narrov range
< 68% oi narrov range High-High Instrument span each steam Instrument span each steam generator generator
TABLE 3.3-5 Continued ENGINEERED SAFETY FEATURES RESPONSE TIN S INITIATING SIGNAL AND FUNCTION
RESPONSE
TIME IN SECONDS 3.
Pressurizer Pressure-Low a.
Safety Injection (ECCS) b.
Reactor Trip (from SI) c.
Feedwater Isolation d.
Containment Isolation-Phase "A"
e.
Containment Purge and Exhaust Isolation
. f.
Motor Driven Auxiliary Feedwater Pumps g.
Essential Service Mater System
< 24.0"/12.0¹
< 2.0
< 8.0
< 18.0¹ Not Applicable
< 60.0
< 48.0~/13.0¹ 4.
Differential Pressure Between Steam Lines-Hi h
a.
Safety Injection (ECCS) b.
Reactor Trip (from SI) c.
Feedwater Isolation d.
Containment Isolation-Phase "A"
e.
Containment Purge and Exhaust Isolation f.
Motor Driven Auxiliary Feedwater Pumps g.
Essential Service Water System
< 12.0¹/24.0¹¹
< 2.0
< 8.0
< 18.0¹/28.0¹¹ Not Applicable
< 60.0
< 13.0¹/48.0¹¹ 5.
Steam Flow in Two Steam Lines - Hi h Coincident with a ~
b.
C.
d.
e.
g.
h.
Tav Low Low Safety Injection (ECCS)
Reactor Trip (from SI)
Feedwater Isolytion Containment Isolation-Phase.
"A" Containment Purge and Exhaust Isolation Auxiliary Feedwater Pumps Essential Service Mater System Steam Line Isolation Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable
< 10 D. C.
COOK - UNIT 2 3/4 3-27 mzwomm wo.
pp 108
3 4.1 REACTIVITY CONTROL SYSTEMS A
S 3 4.1.1 BORATION CONTROL 3 4.1.1.1 and 3 4.1.1.2 SHUTDOWN MARGIN A sufficient SHUTDOWN MARGIN ensures that I) the reactor can be made subcritical from all operating conditions,
- 2) the reactivity transients associated 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.
The most restrictive condition for increased load events occurs at EOL, with T at no load operating temperature, and is associated with a postulate3 steam line break accident and resulting uncontrolled RCS cooldown.
In the analysis of this
- accident, a minimum SHUTDOWN MARGIN of 2.0% hk/k is initially required to control the reactivity transient and automatic ESF is assumed to be available.
Technical Specification requirements call for verification that the SHUTDOWN MARGIN is greater than or equal to that which would be required for the MODE 3 low temperature value, 350'F, prior to blocking safety injection on either the P-II or P-12 permissive interlocks.
This assures in the event of an inadvertent opening of two cooldown steam dump valves that adequate shutdown reactivity is available to allow the operator to identify and terminate the event.
With T
< 200'F, the reactivity transients resulting from a postulated steam line 5Nak cooldown are minimal and a
1% hk/k SHUTDOWN MARGIN provides adequate protection for this event.
In shutdown MODES 4 and 5 when heat removal is provided by the residual heat removal
- system, active reactor coolant system volume may be reduced.
Increased SHUTDOWN MARGIN requirements when operating under these conditions is provided for high reactor coolant system boron concentrations to ensure sufficient time for operator response in the event of a boron dilution transient.
The SHUTDOWN MARGIN requirements are based upon the limiting conditions described above and are consistent with FSAR safety analysis assumptions.
3 4.1.1.3 BORON DILUT ON A minimum flow rate of at least 3000 GPM provides adequate
- mixing, prevents stratification and ensures that reactivity changes will be gradual during boron concentration reductions in the Reactor Coolant System.
A flow rate of at least 3000 GPM will circulate an equivalent Reactor Coolant System volume of 12,612 cubic feet in approximately 30 minutes.
The reactivity change rate associated with boron reductions will therefore be within the capability for operator recognition and control.
D. C.
COOK - UNIT 2 B 3/4 I-l MENDMENT NO. gg,108