ML17334A616
| ML17334A616 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 01/02/1998 |
| From: | John Hickman NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17334A617 | List: |
| References | |
| NUDOCS 9801200127 | |
| Download: ML17334A616 (16) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DIA A MICH A
WE D
DC MENDM Amendment No. 220 License No. DPR-58 The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana Michigan Power Company (the licensee) dated October 8, 1997, and supplemented October 21, 1997, 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 facilitywilloperate 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 willnot be inimical to the common defense and security or to the health and safety of the public; and 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.
980i200i27 980i02 PDR ADQCK 050003i5 P
PDR 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-58 is hereby amended to read as follows:
hni I
ion The Technical Specifications contained in Appendices A and B, as revised through Amendment No?20, 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 issuance, with full implementation within 45 days.
FOR THE NUCLEAR REGULATORY COMMISSION John B. Hickman, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 2,
1998
E S
ENT 220 F
L E
D
-5 D
5 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
~~)EQj.
3/4 6-26 3/4 6-27 B 3/4 5-3 B 3/4 6C 3/4 6-26 3/4 6-27 B 3/4 5-3 B 3/4 6-4
'3/4 LIMITINGCQNDIT FOR OPERATION AND SURYEILL REQUIREMENTS
'3/4.6 CONTAINMENTSYS a MS
/4.6.5 ICE CONDENSER ICE BED IMITINGCONDITION FOR PERATION 3.6.5.1 The ice bed shall be OPERABLE with:
a.
The stored ice having boron concentration of at least 1800 ppm (the boron being in the form of sodium tetraborate),
and a pH of 9.0 to 9.5 at 25'C, b.
Flow channels through the ice condenser, c.
A maximum ice bed temperature of E 27'F, d.
Each ice basket containing at least 1333 lbs of ice, and e.
1944 ice baskets.
~CTION:
With the ice bed inoperable, restore the ice bed to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STANDBYwithin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLAN E RE UIREME TS 4.6.5.1 The ice condenser shaH be determined OPERABLE:
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 using the ice bed temperature monitoring system to verify that th>> maximum ice bed temperature is 6 27'F.
h At least once per IS months by:
Chemical analyses which verify that at least 9 representative samples of stored ice have a boron concentration ofat least 1&00 ppm (the boron being in the form of sodium tetraborate),
and a pH of 9.0 to 9.5 at 25'C.
Weighing a representative sample of at least 144 ice baskets and verifying that each basket contains at least 1333 Ibs of ice.
The representative sample shall include 6 baskets from each of the 24 ioe condenser bays and COOK NUCLEAR PLANT-UNITI Page 3/4 6-26 AMENDMENTSl~ 480 220
. 3/4 LIMITINGCOND S FOR OPERATION AND SURVEIL E REQUIREMENTS
'3/4.6 CONTAINMENTS MS Surveillance Re uiremenis ontinued shall be constituted ofone basket each from Radial Rows 1, 2, 4, 6, 8 and 9 (or from the same row of an adjacent bay ifa basket from a designated row cannot be obtained for weighing) within each bay. Ifany basket is found to contain less than 1333 pounds of ice, a representative sample of 20 additional baskets from the same bay shall be weighed.
The minimum average weight of ice from the 20 additional baskets and the discrepant basket shall not be less than 1333 pounds/basket at a 95% level of confidence.
The ice condenser shall also be subdivided into 3 groups of baskets, as follows:
Group 1 - bays 1 through 8, Group 2 - bays 9 through 16, and Group 3 - bays 17 through 24.
The minimum average ice weight of the sample baskets from Radial Rows 1, 2, 4, 6, 8 and 9 in each group shall not be less than 1333 pounds/basket at a 95% level of confidence.
The minimum total ice condenser ice weight at a 95% level of confidence shall be calculated using all ice basket weights determined during. this weighing program and shall not be less than 2,590,000 pounds.
Verifying, by a visual inspection of at least two flow passages per ice condenser bay, that the accumulation of frost or ice on the top deck floor grating, on the intermediate deck and on flow passages between ice baskets and past lattice frames is restricted to a nominal thickness of 3/8 inches. Ifone fiow passage per'bay is found to have an accumulation of frost or ice greater than this thickness, a representative sample of 20 additional flow passages from the same bay shall be visually inspected.
If these additional fiow passages are found acceptable, the surveillance program may proceed considering the single deficiency as unique and acceptable.
More than one restricted flow passage per bay is evidence of abnormal degradation of the ice condenser.
C.
At least once per 18 months by verifying, by a visual inspection, each ice condenser bay, that the accumulation of frost or ice on the lower inlet plenum support structures and turning vanes is restricted to a nominal thickness of3/8 inches. An accumulation of frost and ice greater than this thickness is evidence of abnor'mal degradation of the ice condenser.
At least once per 40 months by liftingand visually inspecting the accessible portions of at least two ice baskets from each 1/3 of the ice condenser and verifying that the ice baskets are free of detrimental structural wear, cracks, corrosion or other damage.
The ice baskets shall be raised at least 12 feet for this inspection.
COOK NUCLEAR PLANT-UNITI Page 3/46-27 AMENDMENTS,~ ~ 444 220
I t
'/4 BASES 3/4.5 ElVQRGENCY CORE COOLING SYSTEMS
/4.5.5 REFUELING W TER STORA E TANK The OPERABILITYof the RWST as part of the ECCS ensures that sufficient negative reactivity is injected into the core to counteract any positive increase in reactivity caused by RCS system cooldown, and ensures that a sufficient supply ofborated water is available for injection by the ECCS in the event of a LOCA. Reactor coolant system cooldown can be caused by inadvertent deptessurization, a loss of coolant accident or a steam line rupture.
Consistent with the applicable LOCAanalyses~the limitson RWST minimum volume and boron concentration ensure that 1) when combined with'water from melted ice, the RCS, and the accumulators, sufficient water is available within containment to permit recirculation cooling flowto the core, and 2) the reactor willremain subcritical in the cold condition following a LOCA assuming mixing of the RWST, RCS, ECCS water, and other sources of water that may eventually reside in the sump, with all control rods assumed to be out.
The contained water volume limitincludes an allowance forwater not usable because oftank discharge line location or other physical characteristics.
The limits on contained water volume and boron concentration ofthe RWST also ensure a pH value ofbetween 7.6 and 9.5 for the solution recirctiiated within containment after a LOCA. IMs pH.band mittimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components.
The ECCS analyses to determine Fu limits in Speciflcations 3.2.2 and 3.2.6 assumed a RWST water temperature of 70'F. 'IMs temperature value of the RWST water determines that of the spray water initiallydelivered to the containment followingLOCA. It is one ofthe factors which determines the containment back-pressure in the ECCS analyses, performed in accordance with the provisions of 10 CFR 50.46 and Appendix K to 10 CFR 50.
COOK NUCLEARPLANT-UNIT1 Page B 3/4 5-3 AMENDMENTgf ~ 4$$, $44, 220
'3/4 BASES 3/4.6 CONTAINMENTSYSTEMS
/4.6.5 ICE COND SER The. requirements associated with each of the components of the icc condenser ensure that the overall system will be available to provide sufficient pressure suppression capability to limit the containment peak pressure transient to less than 12 psig during LOCA conditions.
The OPERABILITYof thc ice bed ensures that the required ice inventory will 1) be distributed evenly through the containment bays, 2) contain sufficient boron to preclude dilution ofthe containment sump followingthe LOCAand
- 3) contain sufficient heat removal capability to condense the reactor system volume released during a LOCA. These conditions are consistent with the assumptions used in the accident analyses.
The minimum weight figure of 1333 pounds of ice per basket contains a 5% conservative allowance for ice loss through sublimation. In the event that obscrvcd sublimation rates are equal to or lower than design predictions after three yeats ofoperation, the mininnnn ice baskets weight may be adjusted downward.
In addition, the number of ice baskets required to be weighed each 18 months may bc reduced after 3 years of operation ifsuch a reduction is mpported by observed sublimation data.
/4.6.5.2 ICE BED MPERATURE MONITORINGS STEM The OPERABILITYof the ice bed temperature monitoring system ensures that the capability is available for monitoring the ice temperature.
In the event the monitoring system is inoperable, thc ACTION requirements provide assurance that the ice bcd heat removal capacity willbe retained within the specified time limits.
COOK NUCLEhR PLANT-UNXl' Page B 3/4 &4 AMENDMENTam,220
(4.1PR RE00
~o 0O
/g O~
I
~
~0
++*++
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 205554001 DA N
DO 0 ALD DME Amendment No. 204 License No. DPR-74 The U.S. Nuclear Regulatory Commission (the Commission) has found that:
The application for amendment by Indiana Michigan Power Company (the licensee) dated October 8, 1997, and supplemented October 21, 1997, 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 facilitywilloperate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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 willnot 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.
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-74 is hereby amended to read as follows:
i a
The Technical Specifications contained in Appendices A and B, as revised through Amendment No%4, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
This license amendment is effective as of the date of issuance, with full implementation within 45 days.
FOR THE NUCLEAR REGULATORYCOMMISSION John B. Hickman, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 2, 1998
EN OLICE E
ME D
E I
I RA NGLIC E
DP-KET N
-31 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
~(~V 3/4 6-35 3/4 6-36 B 3/4 5-3 B 3/4 6-4 Q~SE j.
3/4 6-35 3/4 6-36 B 3/4 5-3 B 3/4 6-4
3/4 LIMITINGCOND S FOR OPERATION AND SURVEILL
'E REQUIREMENTS 3/4.6 CONTAINMENTSYSTEMS
/4.6.5 ICE CONDENSER CE BED IMITINGCONDITION FOR 0 ERATION 3.6.5.1 The ice bed shall be OPERABLE with:
a.
The stored ice having boron concentration of at least 1800 ppm (the boron being in the form of sodium tetraborate),
and a pH of 9.0 to 9.5 at 25'C, b.
Flow channels through the ice condenser, c.
A maximum ice bcd temperature of 6 27'F, d.
Each ice basket containing at least 1333 lbs of ice, and e.
1944 ice baskets.
I
~CTI ON:
With the ice bed inoperable, restore the ice bed to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least 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 /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
URVEILLANCERE UIRE ENTS 4.6.5.1 The ice condenser shall be determined OPERABLE:
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 using the ice bed temperature monitoring system to verify that the maximum ice bed temperature is 6 27'F.
At least once per 18 months by:
2.
Chemical analyses which verify that at least 9 representative samples of stored ice have a boron concentration of at least 1800 ppm (the boron being in the form of sodium tetraborate),
and a pH of 9.0 to 9.5 at 25'C.
Weighing a representative sample of at least 144 ice baskets and verifying that each basket contains at least 1333 lbs of ice.
The representative sample shall include 6 baskets from each of the 24 ice condenser bays and COOK NUCLEAR PLANT-UNIT2 Page 3/4 6-35 AMENDMENT66, m, 2o4
3/4 LIMITINGCOND FOR OPERATION AND SURVEILL E REQUIREMENTS 3/4.6 CONTAINMENTSYSTEMS SURVEILLANCERE UIREMENTS Continued shall be constituted ofone basket each from Radial Rows I, 2, 4, 6, 8 and 9 (or from the same row of an adjacent bay ifa basket from a designated row cannot be obtained for weighing) within each bay. Ifany basket is found to contain less than 1333 pounds of ice, a r'epresentative sample of 20 additional baskets from the same bay shall be weighed.
The minimum average weight of ice from the 20 additional baskets and the discrepant basket shall not be less than 1333 pounds/basket at a 95% level of confidence.
The ice condenser shall also be subdivided into 3 groups of baskets, as follows:
Group 1-bays I through 8, Group 2-bays 9 through 16, and Group 3-bays 17 through 24.
The minimum average ice weight of the sample baskets from Radial Rows I, 2. 4, 6, 8 and 9 in each group shall not be less than 1333 pounds/basket at a 95% level of confidence.
The minimum total ice condenser ice weight at a 95% level ofconfidence shall be calculated using all ice basket weights determined during this weighing program and shall not be less than 2,590,000 pounds.
3.
Verifying, by a visual inspection of at least two flowpassages per ice condenser bay, that the accumulation of frost or ice on the top deck fioor grating, on the intermediate deck and on flow passages between ice baskets and past lattice frames is restricted to a nominal thickness of 3/8 inches. Ifone flow passage per bay is found to have an accumulation of'frost or ice greater than this thickness, a representative sample of 20 additional fiow passages from the same bay shall be visually inspected. If these additional flow passages are found acceptable, the surveillance program may proceed considering the single deficiency as unique and acceptable.
More than one restricted flow passage per bay is evidence of abnormal degradation of the ice condenser.
At least once per 18 months by verifying, by a visual inspection, of each ice condenser bay, that the accumulation of frost or ice on the lower plenum support structures and turning vanes is restricted to a nominal thickness of3/8 inches.
An accumulation of frost or ice greater than this thickness is evidence of abnormal degradation of the ice condenser.
d.
At least once per 40 months by liftingand visually inspecting the accessible portions of at least two ice baskets from each I/3 of the ice condenser and verifying that the ice baskets are free of detrimental structural wear, cracks, cormsion or other damage.
The ice baskets shall be raised at least 12 feet for this inspection.
COOK NUCLEAR PLANT-UNIT2 Page 3/4 6-36 AMENDMENTQO, 4',
204
t 3/4 BASES 3/4.5 EMERGENCY CORE COOLING SYSTEMS
/4.5.5 REFUELING W TER STOR GE TANK The OPERABILITYof the RWST as part of the ECCS ensures that sufficient negative reactivity is injected into the core to counteract any positive increase in reactivity caused by RCS system cooldown, and ensures that a sufficient supply of borated water is available for injection by the ECCS in the event of a LOCA. Reactor coolant system cooldown can be caused by inadvertent depressurization, a LOCA or steam line rupture.
Consistent with the applicable LOCA analyses>the limits on RWST minimum volume and boron concentration ensure that 1) when combined with water from melted ice, the RCS, and the accumulators, sufficient water is available within containment to permit recirculation cooling flow to the core, and 2) the reactor willremain subcritical in the cold condition following a LOCA assuming mixing of the RWST, RCS, ECCS water, and other sources of water that may eventually reside in the sump, with all control rods assumed to be out.
The contained water volume limitincludes an allowance forwater not usable because oftank discharge line location or other physical characteristics.
The limits on contained water volume and boron concentration ofthe RWST also ensure a pH value ofbetween 7.6 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 caustic stress corrosion on mechanical systems and components.
The ECCS analyses to determine F< limits in Specifications 3.2.2 and 3.2.6 assumed a RWST water temperature of 70'F.
This temperature value of the RWST water determines that of the spray water initiallydelivered to the containnient followingLOCA. Itis one ofthe factors which determines the containment back-pressure in the ECCS analyses, performed in accordance with the provisions of 10 CFR 50.46 and Appendix K to 10 CFR 50, COOK NUCLEARPLANT-UNH' Page B 3/4 5-3 AMENDMENT4%, kQ, 4QQ, 204
t 3/4 BASES 3/4.6 CONTAINMENTSYSTEMS
/4 6.4 CO BUST LE GAS C OL The OPERABILITYof the equipment and systgns required for the detection and control ofhydrogen gas ensures that this equipment willbe available to maintain the hydrogen concentration withincontainment below its flammable limit during post-LOCA conditions.
Either recombiner unit is capable of controlling the expected hydrogen generation associated with 1) zirconium-water reactions, 2) radiolytic decomposition of water and 3) corrosion of metals withincontainment.
These hydrogen control systems are consistent with the recommendations ofRegulatory Guide 1.7, Control of Combustible Gas Concentrations in Containment Following a LOCA," March 1971.
/4.6.5 ICE CO E
SER The requirements associated with each of the components of the ice condenser ensure that the overall system will be available to provide sufficient pressure suppression capability to limit the containment peak pressure transient to less than 12 psig during LOCA conditions.
4.6.5 ICE ED The OPERABILITYof the ice bed ensures that the required ice inventory will 1) be distributed evenly through the containment bays, 2) contain sufficient boron to preclude dilutionofthe containment sump followingthe LOCAand
- 3) contain sufficient heat removal capability to condense the reactor system volume released during a LOCA. These conditions are consistent with the assumptions used in the accident analyses.
The minimum weight figure of 1333 pounds of ice per basket contains a 5% conservative allowance for ice loss through sublimation. In the event that observed sublimation rates are equal to or lower than design predictions after three years ofoperation, the minimum ice baskets weight may be adjusted downward. In addition, the number of ice baskets required to be weighed each 18 months may be reduced after 3 years of operation ifsuch a reduction is supported by observed sublimation data.
/4.6.5.2 ICE BED TEMPERA ONITORING YST The OPERABILITYof the ice bed temperature monitoring system ensures that the capability is avauable for monitoring the ice temperature.
In the event the monitoring system is inoperable, the ACTION requirements provide assurance that the ice bed heat removal capacity willbe retained within the specified time limits.
COOK NUCLEARPLANT-UNIT2 Page B 3/4 &4 AMI<NDMENY4, 444, 204