ML17332A495
| ML17332A495 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 01/05/1995 |
| From: | Hannon J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17332A496 | List: |
| References | |
| NUDOCS 9501100147 | |
| Download: ML17332A495 (16) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C.. 20555-0001 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-315 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
188 License No.
DPR-58 The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana Michigan Power Company (the licensee) dated November 15, 1993 and supplemented October 7,
- 1994, 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 withou't 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.
S5OSSO0>47 esof05 PDR ADOCK 05000315 P
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 B,
as revised through Amendment No.
- 188, 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.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 5,
1995 John N. Hannon, Director Project Directorate III-I Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
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ATTACHMENT TO LICENSE 'AMENDMENT NO.
188 TO 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 vertical lines indicating the area of change.
REMOVE 3/4 4-16 3/4 4-17 3/4 4-17a 3/4 4-17b 3/4 4-18*
B 3/4 4-4 INSERT 3/4 4-16 3/4 4-17 3/4 4-17a 3/4 4-18*
B 3/4 4-4
- Overleaf page provided to maintain document completeness.
No changes contained on, these pages.
EACTO COO STEM OPERAT 0 L LEAKAG IMITING CONDITION FOR OP RAT ON 3.4.6.2 Reactor Coolant System leakage shall be limited to:
a.
No PRESSURE BOUNDARY LEDGE, b.
1 GPM UNIDENTIFIED LEAKAGE, c.
600 gallons per day total primary-to-secondary leakage through all steam generators and 150 gallons per day through any one steam generator for Fuel Cycle 14, d.
10 GPM IDENTIFIED LEDGE from the Reactor Coolant System, e.
Seal line resistance greater than or equal to 2.27E-l ft/gpmz and, f.
The leakage from each Reactor Coolant System Pressure Isolation Valves specified in Table 3.4-0 shall be limited to 0.5 gpm per nominal inch of valve size up to a maximum of 5 gpm, at a Reactor Coolant System average pressure within 20 psi of the nominal full pressure value.
~OTION:
a.
With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT STANDBY within 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 />.
b.
With any.Reactor, Coolant System leakage greater than any one of thy 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 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 />.
c ~
With any reactor coolant system pressure isolation valve(s) leakage greater than the above limit, 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 combination 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 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 />.
Specification 3.4.6.2.e is applicable with average pressure w'ithin 20 psi of the nominal full pressure value.
COOK NUCLEAR PLANT - UNIT 1 3/4 4-16 AMENDMENT NO. 442-,
446-, 474,
$ 88
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CTO COOIANT SYST IMITING CONDITIONS FOR OPERATION Co t nued SURUEIL CE RE UIR E
S 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 during the surveillance must be greater than or equal to 2.27 E-1 ft/gpmz.
The seal line resistance,
- RSI, is determined from the following expression:
R 2.31 (P
P
)
PCHP charging pump header pressure, psig PSI - 2112 psig (low pressure operation) 2262 psig (high pressure operation) 2.31 - conversion factor (12 in/ft) /(62.3 lb/ft )
the total seal in]ectiun 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 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 pressureisolation valve specified in Table 3.4-0 shall be demonstrated OPERABLE pursuant to Specification 4.0.5.
COOK NUCLEAR PIANT - UNIT 1 3/4 4-17 AMENDMENT NO. 442-, 4Qi-, 474, 188
ABLE 4-EACTOR COOLANT SYSTEM PRESSURE SOLATION VALVE Valve Number Valve Size (in.)
Function (
Maximum Allowable Leakage
'gpm)
SI-170L2 10 RH 133 SZ-170L3 10 RH 134 ECCS to Reactor Coolant Loop ¹2 Cold Leg RHR to Reactor Coolant Loop ¹2 Cold Leg ECCS to Reactor Coolant Loop ¹3 Cold Leg RHR to Reactor Coolant Loop ¹3 Cold Leg
) Minimum test differential pressure shall not be below 150 psid'.
COOK NUCLEAR'PIANT - UNIT 1 3/4 4-17a AMENDMENT NO. 462-,
466-, ~,
188
REACTOR COOLANT SYSTEM CHEMISTRY LIMITING CONDITION FOR OPERATION 3.4.7 The Reactor Coolant System chemistry shall be maintained within the limits specified in Table 3.4-1.
APPLICABILITY: At all times.
ACTION:
MODES 1, 2, 3 and 4
a ~
With any one or more chemistry parameter in excess of its Steady State Limit but within its Transient Limit, restore the Parameter to within its Steady State Limit within 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 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 />.
b.
With any one or more chemistry parameter in excess of its Transient Limit, be in at least HOT STANDBY within 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 />.
At all other times With the concentration of either chloride or fIuoride in the Reactor Coolant System in excess of its Steady State Limit for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or in excess of its Transient Limit, reduce the pressur'izer pressure to
< 500 psig, if applicable, and perform an analysis to determine the effects of the out-of-limit condition on the structural integrity of the Reactor Coolant System; determine that the Reactor Coolant System remains acceptable for continued operations prior to increasing the pressurizer pressure above 500 psig or prior to proceeding to MODE 4.
SURVEILLANCE RE UIREMENTS 4.4.7 The Reactor Coolant System chemistry shall be determined to be within the limits by analysis of those parameters at the frequencies specified in Table 4.4-3.
D.C.
COOK - UNIT 1 3/4 4-18
ACTOR COO ANT S S
M BASES Maintaining an operating leakage limit of 150 gpd per steam generator (600 gpd total) for Fuel Cycle 14 will minimize the potential for a large leakage event during steam line break under LOCA conditions.
Based on the NDE uncertainties, bobbin coil voltage distribution and crack growth rate from the previous inspection, the expected leak rate following a steam line rupture is limited to below 12.6 gpm which will limit the calculated offsite doses to within 10 percent of 10 CFR 100 guidelines.
Leakage in the intact loops is limited to 150 gpd. If the projected end of cycle distribution of crack indications results in primary-to-secondary leakage greater than 12.6 gpm in the faulted loop during a postulated steam line break
- event, additional tubes must be removed from service in order to reduce the postulated primary-to-secondary steam line break leakage to below 12.6 gpm.
'A 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 which can be isolated from the balance of the Reactor Coolant System, plant operation may continue provided rhe leak'ng component is promptly isolated from the Reactor Coolant System since isc'ation removes the source of potential failure.
3 4.4 7
CHEMISTRY The limitations on Reactor Coolant System chemistry ensure that corrosion o the Reactor Coolant System is minimized and reduces the potential for Reactor Co"'an=
System leakage or failure due to stress corrosion.
Maintaining the che.-..istry within the Steady State Limits provides adequate corrosion protection to ensure the s ructural integrity of the Reactor Coolant System over the life o
the plant.
The associated effects of exceeding the
Corrosion studies show that operation may be continued with contaminant concentration levels in excess of the Steady S ate Limits, up to the Transient Limits, for the specified limited time ir.-erva's wi hout having a significant effect on the structural integrity of the Reaczcr Coolant System.
The time interval permitting continued operation within che restrictions of the Transient Limits provides time for taking corrective ac iona to restore the contaminant concentrations to within the Steady State Limits.
ROOK NUCLEAR PLANT - UNIT 1 B 3/4 4-4 AMENDMENT NO. S8, 446, ~,
181
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 INDIANA MICKIGAN POWER COMPANY DOCKET NO. 50-316 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. i74 License No.
DPR-74 l.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
B.
C.
D.
E.
The application for amendment by Indiana Hichigan Power Company (the licensee) dated November 15, 1993 and supplemented October 7,
- 1994, 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; The facility will operate 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; 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 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 B,
as revised through Amendment No.
- 174, 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.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance January 5,
1995
.(g John N. Hannon, Director Project Directorate III-I Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
TTACHMENT TO LICENSE AMENDMENT NO.
174 FACILITY OPERATING LICEN. E 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 vertical lines indicating the area of change.
REMOVE 3/4 4-15 3/4 4-16 3/4 4-16a 3/4 4-16b 8 3/4 4-4 INSERT 3/4 4-15 3/4 4-16 3/4 4-16a 8 3/4 4-4
CTOR COOLANT S S
0 RATIONAL LEAKAGE I ITING CONDITION FOR OPERAT ON 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 one steam generator, d.
10 GPM IDENTIFIED LEAKAGE from the Reactor Coolant System, e.
Seal line resistance greater than or equal to 2.27E-l ft/gpmz and, f.
The leakage from each Reactor Coolant System Pressure Isolation Valve specified in Table 3.4-0 shall be limited to 0.5 gpm per nominal inch of valve size up to a maximum of 5 gpm, at a Reactor Coolant System average pressure within 20 psi of the nominal full pressure value.
~CTION:
a.
'With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT STANDBY within 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 />.
- b. Mth any Reactor Coolant System leakage greater than any one of the above limits, excluding PRESSURE BOUNDARY LEAKAGE, reduce the leakage rate to within 1'imits 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 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 t'e following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
c.
'Pith any reactor coolant system pressure isolation valve(s) leakage greater than the above limit, 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 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 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 />.
Specification 3.4.6.2.e is applicable with average pressurizer pressure within 20 psi of the nominal full pressure value.
COOK NUCLEAR PLANT - UNIT 2 3/4 4-15 AMENDMENT NO. 444
~ "74
A OR COOLANT SYS IM TING COND TIONS FOR 0 ERAT ON Conti ued SURVEILLANCE RE UIREMENTS 4.4.6.2.1 Reactor Coolant System leakages shall be demonstrated to be within each of the above limits by; 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 during the surveillance must be greater than or equal to 2.27 E-1 ft/gpm~.
The seal line resistance,
- RS1, is determined from the following expression:
R 2.31(P P
)
CHP SI where:
PCHP charging pump header pressure, psig PSI - 2262 psig (high pressure operation) 2.31 conversion factor (12 in/ft) /(62.3 lb/ft )
Q
- the total seal injection flow, gpm The provisions of Specification 4.0.4 are not appli'cable 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 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 pursuant to Specification 4.0.5.
COOK NUCLEAR PLANT - UNIT 2 3/4 4-16 AMENDMENT NO. 446 174
EACTOR COOLANT SYSTEM PRESSURE SO TIO V LVE Valve Number Valve Size (in.)
Function
(
Maximum
,Allowable Leakage (gpm)
SI-170L2 10 RH 133 8
SI-170L3 10 RH 134 8
ECCS to Reactor Coolant Loop ¹2 Cold Leg RHR to Reactor Coolant Loop ¹2 Cold Leg ECCS to Reactor Coolant Loop ¹3 Cold Leg RHR to Reactor Coolant Loop ¹3 Cold Leg
) Minimum test differential pressure shall not be below 150 psid.
COOK NUCLEAR PLANT - UNIT 2 3/4 4-16a AMENDMENT NO. 446 )
174
CTO 00
]USE S 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 flow that is diverted from the boron in]ection line to the seal in]ection 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 ensures that the dosage contribution from the tube leakage willbe 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 with 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 which 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.
3 4 4 7 CHEMIS Y
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 within 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 show that operation may be continued with contaminant concentration levels in excess of the Steady State Limits, up to the Transient Limits, for the specified limited time intervals without having a
significant effect on the structural integrity of the Reactor Coolant System.
The time interval permitting continued operation within the restrictions of the Transient Limits provides time for taking corrective actions to restore the contaminant concentrations to within the Steady State Limits.
COOK NUCLEAR PLANT - UNIT 2 B 3/4 4-4 AMENDMENT NO.
~M
, 444, 174