ML17325A742
| ML17325A742 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 05/19/1988 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Indiana Michigan Power Co |
| Shared Package | |
| ML17325A745 | List: |
| References | |
| DPR-58-A-115, DPR-74-A-101 NUDOCS 8805270063 | |
| Download: ML17325A742 (11) | |
Text
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gO kg**4 UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-315 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. I15 License No.
DPR-58 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana Michigan Power Company (the licensee) dated November 2, 1987, 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.
D.
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; 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.
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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-58 is hereby amended to read as follows:
Technical S ecifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No.
f15
, 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.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 19, 1988 Daniel R. Muller, Acting Director Project Directorate III"1 Division of Reactor Projects - III, IV, V 8 Special Projects
UNITED STATES NUCLEAR REGULATORY COMMISSION 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. 101 License No.
DPR-74 l.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana Michigan Power Company (the licensee) dated November 2, 1987, 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.
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:
Technical S ecifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No.
- 101, 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.
FOR THE NUCLEAR REGULATORY COMMI SION
Attachment:
Changes to the Technical Specifications Date of Issuance:
May I9 I988 Daniel R. Muller, Acting Director Project Directorate III-1 Division of Reactor Projects - III, IV, V 8 Special Projects
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO.II5 FACILITY OPERATING LICENSE NO.
DPR-58 AMENDMENT NO. 101FACILITY OPERATING LICENSE NO.
DPR-74 DOCKETS NOS.
50-315 AND 50-316 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 marginal lines indicating the area of change.
REMOVE 3/4 11-8 3/4 11-9 3/4 ll-ll 3/4 11-8 3/4 11-9 3/4 ll"11 UNIT 1 UNIT 2 INSERT 3/4 11-8 3/4 11-9 3/4 11-11 3/4 11-8 3/4 11-9 3/4 11-11
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TABLE 4.11-2 (cont)
TABLE NOTATION a.
The lower limit of detection (LLD) is defined in Table Notation a.
of Table 4.12-1 of Specification 4.12.1.1.
b.
Analyses shall also be performed following any operational occurrence which has altered the mixture of radionuclides as indicated by RCS analysis.
(i.e., start-up.)
c ~
Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing.
Analyses shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for 7 days following each shutdown, startup or similar operational occurrence which lead to significant increases or decreases in radioiodine in the Reactor Coolant System.
When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLD's may be increased by a factor of 10.
d.
The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specification 3.11 '.1, 3.11.2.2, 3.11.2.3.
e.
The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides:
Kr-87, Kr-88, Xe-133, Xe-133M, Xe-135 and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for, particulate emissions.
This list does not mean that only these nuclides are to be detected and reported.
Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.
f.
Releases from incinerated oil are discharged through the Auxiliary Boiler System.
Releases shall be accounted for based on pre-release grab sample data.
g.
Samples of waste oil to be incinerated shall be collected from the container in which the waste oil is stored (e.g.,
waste oil storage
- tank, 55 gal.
drums) prior to transfer to the Auxiliary Boiler System and shall be representative of container contents.
D. C.
COOK - UNIT 1 3/4 11-9 Amendment No.
116
RADIOACTIVE EFFLUENTS DOSE RADIOIODINES RADIOACTIVE MATERIAL IN PARTICUIATE FORM AND RADIONUCLIDES OTHER THAN NOBLE "GASES LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to A MEMBER OF THE PUBLIC from radioiodine, radioactive materials in particulate form, and radionuclides other than noble gases with half-lives greater than 8 days in gaseous effluents released to unrestricted areas shall be limited to the following:
a.
During any calendar quarter to less than or equal to 7.5 mrem to any organ; b.
During any calendar year to less than or equal to 15 mrem to any organ; c.
Less than 0.1% of the 3.11.2.3 (a) and (b) limits as a result of burning contaminated oil.
APPLICABILITY: At all times.
ACTION:
a ~
With the calculated dose from the release of radioiodines, radioactive materials in particulate form, or radionuclides other than noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions taken to reduce the releases and the proposed corrective action to be taken to assure that subsequent release will be within the above limits.
The provisions of Specification 3.0.3, 3.0.4, and 6.9.1.13 are not applicable.
SURVEILLANCE RE UIREMENTS 4.11.2.3 DOSE CALCUIATIONS Cumulative dose contributions for the total time period shall be determined in accordance with the ODCM at least once every 31 days.
D. C.
COOK - UNIT 1 3/4 11-11 Amendment No.
115
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TABLE 4. 11-2 (cont)
TABLE NOTATION a.
The lower limit of detection (LLD) is defined in Table Notation a.
of Table 4.12-1 of Specification 4.12.1.1.
b.
Analyses shall also be performed following any operational occurrence which has altered the mixture of radionuclides as indicated by RCS analysis.
(i.e., start-up.)
C.
Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing.
Analyses shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for 7 days following each shutdown, startup or similar operational occurrence which lead to significant increases or decreases in radioiodine in the Reactor Coolant System.
When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLD's may be increased by a factor of 10.
d.
The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specification 3.11 '.1, 3.11 '.2, 3.11.2.3.
The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides:
Kr-87, Kr-88, Xe-133, Xe-133M, Xe-135 and Xe-138 for gaseous emissions and Mn-54, Pe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions.
This list does not mean that only these nuclides are to be detected and reported.
Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.
f.
Releases from incinerated oil are discharged through the Auxiliary Boiler System.
Releases shall be accounted for based on pre-release grab sample data.
g.
Samples of waste oil to be incinerated shall be collected from the container in which the waste oil stored (e.g.,
waste oil storage
- tank, 55 gal. drums) prior to transfer to the Auxiliary Boiler System and shall be representative of container contents.
D.
C.
COOK - UNIT 2 3/4 11-9 Amendment No. 110
RADIOACTIVE EFFLUENTS DOSE RADIOIODINES RADIOACTIVE MATERIAL IN PARTICULATE FORM AND RADIONUCLIDES OTHER THAN NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to A MEMBER OF THE PUBLIC from radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases with half-lives greater than 8 days in gaseous effluents released to unrestricted areas shall be limited to the following:
a.
During any calendar quarter to less than or equal to 7.5 mrem to any organ; b.
During any calendar year to less than or equal to 15 mrem to any organ; c.
Less than 0.18 of the 3.11.2.3(a) and (b) limits as a result of burning contaminated oil.
APPLICABILITY: At all times'CTION:
Pith the calculated dose from the release of radioiodines, radioactive materials in particulate form, or radionuclides other than noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions taken to reduce the releases and the proposed corrective action to be taken to assure that subsequent release will be within the above limits.
b.
The provisions of Specification 3.0.3, 3.0.4, and 6.9.1.13 are not applicable.
SURVEILLANCE RE UIREMENTS 4.11.2.3 DOSE CALCUIATIONS Cumulative dose contributions for the total time period shall be determined in accordance with the ODCM at least once every 31 days.
D. C.
COOK - UNIT 2 3/4 11-11 Amendment No. 110