ML17329A386
| ML17329A386 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/13/1992 |
| From: | March L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17329A387 | List: |
| References | |
| NUDOCS 9202250320 | |
| Download: ML17329A386 (15) | |
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%**y 4 UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-315 I
DONALD C.
COOK NUCLEAR PLANT 'NIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
License No. DPR-58 l.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana Michigan Power Company (the licensee) dated October 17, 1989, 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 cotton 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.
9202250320 920213 PDR ADOCK 050003i5 P
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-58 is hereby amended to read as follows:
The Technical Specifications contained in Appendices A
and B, as revised through Amendment No.
162 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 L. B. Harsh, Director Project Directorate III-1 Division of Reactor Projects III/IY/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specif ications Date of Issuance:
February 13, 1992
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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. i46 License No. DPR-74 l.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Indiana Michigan Power Company (the licensee) dated October 17, 1989, 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 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 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:
The Technical Specifications contained in Appendices A
and 8, as revised through Amendment No.
146 are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Speci ficat ions.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION L. B. Marsh, Director Project Directorate III-I Division of Reactor Projects III/IV/Y Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 13, 1992
ATTACHMENT TO LICENSE AMENDMENT NO.
FACILITY OPERATING LICENSE NO. DPR-58 DOCKET NO. 50-315 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 4-16 3/4 4-17 3/4 4-17a B 3/4 4-3 INSERT 3/4 4-16 3/4 4-17 3/4 4-17a B 3/4 4-3
REACTOR COO~
SYSTEM OPERATIONAL LEAXAGE LIMITING CONDITION FOR OPERATION 3.4.6.2 Reactor Coolant System leakage shall be limited to:
a.
No PRESSURE BOUNDARY LEAXAGE, b.
1 GPM UNIDENTIFIED LEAKAGE, c.
1 GPM total primary-to-secondary leakage through all steam generators and 500 gallons per day through any one steam generator, d.
10 GPM IDENTIFIED LEAKAGE from the Reactor Coolant System, e.
Seal line resistance greater than or equal to 2.27 E-1 ft/gpm
- and, 2
f.
1 GPM leakage from any reactor coolant system prcssure isolation valve specified in Table 3.4-0.
hPPLICABILITY:
MODES 1, 2, 3 and 4~
hCTZON:
a, With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT STANDBY vithin 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN vithin the folloving 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
With any Reactor Coolant System leakage greater than any one of the above limits, excluding PRESSURE BOUNDARY LEAKAGE, reduce the leakage rate to vithin limits vithin 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT STANDBY vithin 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 vithin the folloving 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
c.
With any reactor coolant system pressure isolation valve(s) leakage greater than the above limit, except vhen; 1.
The leakage is less than or equal to 5.0 gpm, and 2.
The most recent measured leakage does not exceed the previous measured leakage* by an amount that reduces the AMENDMENT NO. 162 Order dated April 20, 1981 Mo satisfy hLARA requirements, measured leakage may be measured indirectly (as from the performance of pressure indicators) if accomplished in accordance vith approved procedures and supported by computations shoving that the method is capable of demonstrating valve compliance vith the leakage criteria.
~Specification 3.4.6.2.e is applicable vith average pressuriser prcssure vithin 20 psi of the nominal full pressure value.
COOK NUCLEAR PLANT - UNIT 1 3/4 4-16
REACTOR COOLANT SYSTEM LIMITING CONDITION POR OPERATION Continued margin between the most recent measured leakage and the maximum limit of 5.0 gpm by 50% or more, declare the leaking valve inoperable and isolate the high pressure portion of the affected system from the low pressure portion by the use of a combina'tion of at least two closed valves, one of which may be the OPERABLE check valve and the other a closed de-energized motor operated valve.
Verify the isolated condition of the closed de-energized motor operated valve at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or be in at least HOT STANDBY within the next 6
hours 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 />.
SURVEILLANCE RE UIREMENTS 4.4.6,2.1 Reactor Coolant System leakages shall be demonstrated to be within each of the above limits by:
a.
Monitoring the containment atmosphere particulate radioactivity monitor at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b.
Monitoring the containment sump inventory and discharge at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
c.
Determining the seal line resistance at least once per 31 days when the average pressurizer pressure is within 20 psi of its nominal full pressure value.
The seal line resistance measured during2the surveillance must be greater than or equal to 2.27 E-1 ft/gpm The seal line resistance, RSL, is determined from the following expression:
PCHP charging pump header pressure, psig PSI 2 1 12 psig (low pressure operation) 2262 psig (high pressure operation) 2.31 conversion factor (12 in/ft) /(62.3 lb/ft )
2 3
Q the total seal in]ection flow, gpm The provisions of Specification 4.0.4 are not applicable for entry into MODES 3 and 4.
d.
Performance of a Reactor Coolant System water inventory balance at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> during steady state operation, and COOK NUCLEAR PIJQiT - UNIT 1 3/4 4-17 AMENDMENT NO. )Q, Order dated Apnl 20, 1981
REACTOR COOLANT SYSTEM SURVEILLANCE RE UIREMENTS Continued e.
Monitoring the reactor head flange leakoff system at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4.4.6.2.2 Each reactor coolant system pressure isolation valve specified in Table 3.4-0 shall be demonstrated OPERABLE by verifying leakage to be vithin its limit prior to entering MODE 3:
a.
After each refueling outage; b.
Whenever the plant has been in COLD SHUTDOWN for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or more and if leakage testing has not been performed in the previous 9
months; c.
Prior to returning the valve to service following maintenance, repair or replacement work on the valve.
COOK NUCLEAR PLANT - UNIT 1 3/4 4-17a AMENDMENT NO 162 Order dated April 20, 1981
REACTOR COOIhNT SYSTEM 3 4.4.6 REACTOR COOLANT SYSTEM LEAKAGE 3 4.4.6.1 LEAKAGE DETECTION SYSTEMS The RCS leakage detection systems required by this specification are provided to monitor and detect leakage from the Reactor Coolant Pressure Boundary.
These detection systems are consistent vith the recommendations of Regulatory Guide 1.45, "Reactor Coolant Pressure Boundary Leakage Detection Systems,"
May 1973.
3 4.4.6.2 OPERATIONAL LEAKAGE Industry experience has shovn that while a limited amount of leakage is expected from the
- RCS, the unidentified portion of this leakage can be reduced to a threshold value of less than 1 gpm.
This threshold value is sufficiently lov to ensure early detection of additional leakage.
The 10 GPM IDENTIFIED LEAKAGE limitations provides allovance for a limited amount of leakage from known sources vhose presence will not interfere vith the detection of UNIDENTIFIED LEAKAGE by the leakage detection systems'he limitation on seal line resistance ensures that the seal line resistance is greater than or equal to the resistance assumed in the minimum safeguards LOCA analysis.
This analysis assumes that all of the flow that is diverted from the boron in]ection line to the seal injection line is unavailable for core cooling.
COOK NUCLEAR PLANT - UNIT 1 B 3P 4-3 AMENDMENT NO. g, g, fg', )Q
ATTACHMENT TO LICENSE AMENDMENT NO.
>46 FACILITY OPERATING LICENSE NO. DPR-74 DOCKET NO. 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 4-15 3/4 4-16 3/4 4-16a 8 3/4 4-4 INSERT 3/4 4-15 3/4 4-16 3/4 4-16a B 3/4 4-4
REACTOR COODLNT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.6.2 Reactor Coolant System leakage shall be limited to:
a.
No PRESSURE BOUNDARY LEAKAGE, b.
1 GPM UNIDENTIFIED LEAKAGE, c.
1 GPM total primary-to-secondary leakage through all steam generators and 500 gallons per day through any onc steam generator, d.
10 GPM IDENTIFIED LEAKAGE from the Reactor Coolant System, 2
e.
Seal line resistance greater than or equal to 2.27 E-1 ft/gpm, and f.
1 GPM leakage from any reactor coolant system pressure i,solation valve specified in Table 3.4-0.
APPLICABILITY:
MODES 1, 2, 3 and 4~
ACTION:
a, Vith any PRESSURE BOUNDARY LEAKAGE, be in at least HOT STANDBY vithin 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOVN within the folloving 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
Vith any Reactor Coolant System leakage greater than any one of the above limits, excluding PRESSURE BOUNDARY LEAKAGE, reduce the leakage rate to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT STANDBY vithin 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 SHUTDOVN vithin the folloving 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
c.
Vith any reactor coolant system pressure isolation valve(s) leakage greater than the above limit, except vhen:
1.
The leakage is less than or equal to 5.0 gpm, and 2.
The most recent measured leakage does not exceed the previous measured l.eakage* by an amount that reduces the Wo satisfy ALARA requirements, measured leakage may be measured indirectly (as from the performance of pressure indicators) if accomplished in accordance vith approved procedures and supported by computations shoving that the method is capable of demonstrating valve compliance vith the leakage criteria.
~Specification 3.4.6.2,e is applicable vith average prcssuriser pressure vithin 20 psi of the nominal full prcssure value.
COOK NUCLEAR PLANT - UNIT 2 3/4 4-15 AMENDMENT NO.
146 Order dated Apn) 20 1981
REhCTOR COOKOFF SYSTEM LIMITING CONDITION FOR OPERATION Continued margin between the most recent measured leakage and the maximum limit of 5.0 gpm by 50% or more, declare the leaking valve inoperable and isolate the high pressure portion of the affected system from the low pressure portion by the use of at least two closed valves, one of which may be the OPERhSLE check valve and the other a closed de-energised motor operated valve.
Verify the isolated condition of the closed de-energised motor operated valve at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or be in it least HOT SThNDBY 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 />.
SURVEILLhNCE RE UIREMENTS 4.4.6.2.1 Reactor Coolant System leakages shall be demonstrated to be within each of the above limits by:
a.
Monitoring the containment atmosphere particulate radioactivity monitor at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b.
Monitoring the containment sump inventory and discharge at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
c.
Determining the seal line resistance at least once per 31 days when the average pressurizer pr~ssure is within 20 psi of its nominal full pressure value.
The seal line resistance measured during the surveillance must be greater than or equal to 2.27 E-1 ft/gpm The seal line resistance, RSL, is determined from the following expression:
SL 2'31 (
CHP SI Q2 where:
PCHP charging pump header pressure, psig PSZ 2262 ps ig (high pressure operation) 2.31 conversion factor (12 in/ft) /(62.3 lb/ft )
2 3
the total seal in]ection flow, gpm The provisions of Specification 4.0.4 ire not applicable for entry into MODES 3 and 4.
Performance of a Reactor Coolant System water inventory balance at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> during steady state operation, and COOK NUCLEhR PXhNT - UNIT 2 3/4 4-16 hMENDMENT NO.
f46 Order dated Ppr il 20, 1981
REACTOR COOLANT SYSTEM SURVEILLANCE RE UIREMENTS Continued e.
Monitoring the reactor head flange leakoff y
s stem at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
re solation val~e specified 4.4.6.2.2 Each reactor coolant system pressure isol in Ta e
. <<s bl 3 4<<0 hall be demonstrated OPERABLE pursuant to Specification e t that in lieu of any leakage testing require y
p ed b S acification 4.0.5, except t a n
d OPERABLE b verifying leakage to be 4.0.5, each valve shall be demonstrate vithin its limit prior to'ntering MODE 3:
a, After each refueling outage; b
Vh ever the plant has been in COLD SHUTDOVN for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or more eneve and if leakage testing has not been performed in p
the revious 9
months; c.
Prior to returning the valve to service folloving maintenance, repair or replacement work on the valve.
COOK NUCLEAR PLANT - UNIT 2 3/4 4-16a AMENDMENT NO.
der dated Apnea 20
~9@
REACTOR COOLANT SYSTEM The limitation on seal line resistance ensures that the seal line resistance is greater than or equal to the resistance assumed in the minimum safeguards LOCA analysis.
This analysis assumes that all of the flov that is diverted from the boron injection line to the seal injection line is unavailable for core cooling.
The total steam generator tube leakage limit of 1 GPM for all steam generators not isolated from the RCS ensuzes that the dosage contribution from the tube leakage vill be limited to a small fraction of Part 100 limits in the event of either a steam generator tube rupture or steam line break.
The 1
GPM limit is consistent vith the assumptions used in the analysis of these accidents.
The 500 gpd leakage limit per steam generator ensures that steam generator tube integrity is maintained in the event of a main steam line rupture or under LOCA conditions.
PRESSURE BOUNDARY LEAKAGE of any magnitude is unacceptable since it may be indicative of an impending gross failure of the pressure boundary.
Should PRESSURE BOUNDARY LEAKAGE occur through a component vhich can be isolated from the balance of the Reactor Coolant System, plant operation may continue provided the leaking component is promptly isolated from the Reactor Coolant System since isolation removes the source of potential failure.
The Surveillance Requirements for RCS Pressure Isolation Valves provide added assurance of valve integrity thereby reducing the probability of gross valve failure and consequent intersystem LOCh,.
Leakage from the RCS Pressure Isolation Valves is IDENTIFIED LEAKAGE and vill be considered as a portion of the alloved limit.
3 4.4.7 CHEMISTRY AMENDMENT NO. N, 146 B 3/4 4-4 The limitations on Reactor Coolant System chemistry ensure that corrosion of the Reactor Coolant System is minimized and reduces the potential for Reactor Coolant System leakage or failure due to stress corrosion.
Maintaining the chemistry vithin the Steady State Limits provides adequate corrosion protection to ensure the structural integrity of the Reactor Coolant System over the life of the plant.
The associated effects of exceeding the oxygen, chloride, and fluoride limits are time and temperature dependent.
Corrosion studies shov that operation may be continued vith contaminant concentration levels in excess of the Steady State Limits, up to the Transient Limits, for the specified limited time intervals vithout having a significant effect on the structural integrity of the Reactor Coolant System.
The time interval permitting continued operation vithin the restrictions of the Transient Limits provides time for taking corrective actions to restore the contaminant concentrations to vithin the Steady State Limits.
COOK NUCLEAR PLANT - UNIT 2