ML17335A239
| ML17335A239 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 09/17/1998 |
| From: | Stang J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17335A240 | List: |
| References | |
| NUDOCS 9809250248 | |
| Download: ML17335A239 (14) | |
Text
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D OW UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON> D.C. 205554001 D
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Amendment No. 223 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 March 3, 1998, 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 1; 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 willbe 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-58 is hereby amended to read as follows:
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Te hnical a ions The Technical Specifications contained in Appendices A and B, as revised through Amendment No.~, 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 G
hn F. Stang, Sr.
roject 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:
Sepuxiber 17, 1998
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20~001 LICENSE ND E
NO 223 OFAC L E
ING SE DP ET 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.
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3/4 LIMI'IINGCONDITIONS FOR OPERATION AND SURVEILLANCEREQUIIKMIDfIS 3/4.6'ONTAINMENTSYSTEMS Verifying during a recombiner system functional test that the heater sheath temperature increases to a 1200'F within 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> and is maintained for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
4.
Verifying the integrity of all heater electrical circuits by performing a continuity and resistance to ground test following the above required functional test.
The resistance to ground for any heater phase shall be a 10,000 ohms.
COOK NUCLEAR PLANT-UNITI Page 3/4 6-25 AMENDMENT 223
3/4 BASES 3/4.6 CONTAINMENTSYSTEMS
'Re OPERABILITYofthe containment spray system ensures that containment depressurization and cooling capability willbe available in the event of a LOCA. The pressure reduction and resultant lower containment leakage rate are consistent with thc assumptions used in the accident analyses.
The OPERABILITYofthe spray additive system ensures that sufficient NaOH is added to the containment spray in the event of a LOCA. The limits on NaOH minimum volume and concentration, ensure that 1) the iodine removal efficiency of the spray water is maintained because of the increase in pH value, and 2) corrosion effects on components within containment are mininuzcd.
These assumptions are consistent with the iodine removal efficiency assumed in the accident analyses.
The OPERABILITYofthe containment isolation valves ensures that the containment atmosphere willbe isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment.
Containment isolation within the time limits specified ensures that thc release of radioactive material to the environment willbe consistent with the assumptions used in the analyses for a LOCA.
'lhe opening of containment purge and exhaust valves and locked or sealed closed containmcnt isolation valves on ari intermittent basis under administrative conuol includes the following considerations:
(1) stationing a qualified individual, who is in constant communication with control room, at the valve controls, (2) instructing this individual to close these valves in an accident situation, and (3) assuring that environmental conditions willnot preclude access to close the valves and that this action willprevent thc release of radioactivity outside the containment.
The OPERABILITYof the equipment and systems required for the detection and control ofhydrogen gas ensures that this equipment willbe available to maintain the hydrogen concentration within containment 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 within containment.
The acceptance criterion of 10,000 ohms is based on the test being performed with the heater element at an ambient temperature, but can be conservatively applied when the heater element is at a temperature above ambient.
COOK NUCLEARPLANT-UNITI Page B 3/4 6-3 AMENDMENT~ 223
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 D
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TN LIC Amendment No, 207 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 March 3, 1998, 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 1; 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 will not be inimical to the common defense and security or to the health and safety of the public; and E.'he issuance of this amendment is in accordance with 10 CFR Part 51 of,the Commission's regulations and all applicable requirements have been satisfied.
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'perating License No. DPR-74 is hereby amended to read as follows:
0 (2) ch 'l S e ifi a i The Technical Specifications contained in Appendices A and B, as revised through Amendment No.7, 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 REGULATORY COMMISSION Jo n F. Stang, Sr. Pr ]ect 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: >P~ >>> >998
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&0001 T
C E T 207 CILI 0
E ING I
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-7 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.
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3/4 BASES 3/4.6 CONTAINMENTSYSIXMS The OPERABILITYof the equipment and systems required for the detection and control ofhydrogen gas ensures that this equipment willbe available to maintain the hydrogen concentration within containment below its flammable limit during post-LOCA conditions.
Either recombiner unit is capable of controlling the expected hydrogen generation associamd with: i) zirconiom-wamr reactions; 2) radiolyuc decomposhion ofwater; and 3) cormsion of meuds widdn containment.
Thcsc hydrogen control systems are consistent with the recommendations of Regulatory Guide 1.7, Control of Combustible Gas Concentrations in Containmcnt Following a LOCA," March 1971.
The acceptance criterion of 10,000 ohms is based on the test being performed with the heater element at an ambient temperature, but can be conservatively applied when the heater element is at a temperature above ambient.
The requirements associated with each of the components of the ice, condenser ensure that the overall system willbe available to provide sufficient prcssure suppression capability to limit the containment peak pressure transient to less than 12 psig during LOCA conditions.
The OPERABILITYof the ice bed ensures that the required ice inventory will I) bc distributed evenly through the containment bays, 2) contain sufficient boron to preclude dilution of the containment sump following thc LOCA and-
- 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.
Thc minimum weight figure of 1333 pounds of icc pcr basket contains a S% conservative allowance for ice loss through sublimation.
In the cvcnt that observed sublimation rates are equal to or lower than design predictions after three years of operation, 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.
The OPERABILITY of the ice bed temperature monitoring system ensures that the capability is available for monitoring the ice temperature.
In the cvcnt 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 NUCLEAR PLANT-UNIT2 Page B 3/4 &4 AMENDMENT%, ~, 284 207
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