ML20093E950
| ML20093E950 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  (DPR-24-A-163, DPR-27-A-167) |
| Issue date: | 10/12/1995 |
| From: | Hansen A NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20093E953 | List: |
| References | |
| NUDOCS 9510170182 | |
| Download: ML20093E950 (13) | |
Text
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UNITED STATES g
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,j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 206t50001 49.....,o WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-266 POINT BEACH NVCLEAR PLANT. UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 163 License No. DPR-24 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated January 26, 1994, as supplemented by letters dated December 1, 1994 and June 23, 1995, 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.
l 9510170182 951012 PDR ADOCK 05000266 P
2.
Accordingly, the license is amended by changes to the Technical specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No.
DPR-24 is hereby amended to read as follows:
B.
Igshnical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.163, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective immediately upon issuance.
The
' Technical Specifications are to be implemented within 45 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION flA
^
Allen G. Hansen, Project Manager l
Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
October 12, 1995 i
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UNITED STATES 4
S NUCLEAR REGULATORY COMMISSION If WASHINGTON. D.C. 1066 & 4001 I
WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-301 POINT BEACH NUCLEAR PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 167 License No. DPR-27 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated January 26, 1994, as supplemented by letters dated December 1, 1994 and June 23, 1995, 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; l
C.
There is reasonable assurance (1) 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; 1
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 4
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, l
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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 3.B of Facility Operating License No.
DPR-27 is hereby amended to read as follows:
B.
Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.167, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective immediately upon issuance. The Technical Specifications are to be implemented within 45 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION i
Allen G. Hansen, Project Manager Project Directorate III-3 4
Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: October 12, 1995 i
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ATTACHMENT TO LICENSE AMENDMENT NOS.163 AND167 TO FACILITY OPERATING LICENSE NOS. DPR-24 AND DPR-27 DOCKET NOS. 50-266 AND 50-301 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by amendment number and contain marginal lines indicating the area of change.
4 REMOVE INSERT TS 15.3.0-1 through TS 15.3.0-1 through 15.3.0-5 (5 pages) 15.3.0-6 (6 pages)
TS 15.3.3-6 TS 15.3.3-6 i
TS 15.3.3-7 TS 15.3.3-7 i
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15.3 Limitina Conditions for Ooeration 15.3.0 General Considerations A.
Many of the Limiting Conditions for Operation (LCO) presented in these specifications provide a temporary relaxation of the single failure criterion, which is consistent with overall reliability considerations, to allow time periods during which 1
corrective action may be taken to restore the system to full l
operability.
If the situation has not been corrected within the specified time period, and the LCO prescribes no other specific action, action shall be initiated within one hour to place the affected unit in:
1.
Hot shutdown within seven hours of entering this specification; AND 2.
Cold shutdown within 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br /> of entering this l
specification.
This specification is applicable during power operation, low power operation, and shutdown with temperature 2200*F.
l B.
In the event an LC0 cannot be satisfied because of equipment failures or limitations beyond those specified in the permissible conditions of the LCO, action shall be initiated within one hour to place the affected unit in:
l 1.
Hot shutdown within seven hours of entering this specification; AND 2.
Cold shutdown within 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br /> of entering this specification.
This specification is applicable during power operation, low power operation, and shutdown with temperature 2200'F C.
Upon discovery of a Limiting Condition for Operation, the actions delineated in the specification shall be performed, i
If the requirements of the Limiting Condition for Operation are met or are no longer applicable prior to the expiration of the times delineated in the specification, completion of the i
specified actions is not required, unless otherwise stated.
Unit 1 - Amendment M,163 15.3.0-1 Unit 2 - Amendment M,167
i-D.
When a system, subsystem, train, component or device is i
determined to be inoperable solely because its emergency l
power source is inoperable, or solely because its normal power source is inoperable, the system, subsystem, train,
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component' or device may be considered operable for the purpose of satisfying the requirements of the applicable LCO, provided:
1.
The available power source (normal or emergency) is
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operable; AND 2.
All required redundant system (s), subsystem (s),
train (s), compo'nents(s) and device (s) are operable, j
If either 15.3.0.D.1 or 15.3.0.D.2 cannot be met, specifications 15.3.0.A and 15.3.0.B become applicable. This l
specification is not applicable during cold shutdown or l
refueling shutdown conditions.
l E.
A momentary loss of normal or emergency power resulting in prompt corrective or required action in accordance with Table j
15.3.5-2, i.e., placing associated channels into the trip condition or shutdown of the unit, shall not be interpreted as causing a violation of the specification with respect to q
minimum operable channels, unless said loss is the result of l
personnel error or procedural violation.
l F.
Equipment removed from service or declared inoperable to comply with required actions may be returned to service solely i
to perform testing required to demonstrate its operability or the operability of other equipment.
Bases Specifications 15.3.0.A and 15.3.0.B delineate the actions to be taken for i
circumstances not directly provided for in the action statements of a Limiting l
Condition for Operation (LCO) and whose occurrence would violate the intent of the specification. These specifications delineate the time limits for placing the unit (s) in a safe condition when operation cannot be maintained within the limits for safe operation as defined by the LCO and its associated action statements.
It is not intended to be used as an operational convenience that permits routine, voluntary I
removal of redundant systems or components from service in lieu of other alternatives Unit 1 - Amendment 60rB9,163 15.3.0-2 Unit 2 - Amendment 66rHB,167
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that would not result in redundant systems or components being inoperable.
Upon entering 15.3.0.A or 15.3.0.B, one hour is allowed to prepare for an orderly shutdown before initiating a change in unit operation. This includes time to permit l
the operator to coordinate the reduction in electrical generation with system control to ensure the stability and availability of the electrical grid. The time limits specified to reach hot and cold shutdown permit the shutdown to proceed in a controlled and orderly manner that is well within the capabilities of the unit (s),
assuming that only the minimum required equipment is operable. This reduces thermal stresses on components of the Reactor Coolant System and the potential for a plant transient that could. challenge plant safety systems.
If the requirements of a Limiting Condition for Operation are not met, specifications
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in Section 15.3.0 delineate time limits for completing the actions within the I
associated action statement.
Should an action statement specify more than one action, each action has its own time limit. Each time limit in Section 15.3.0 is referenced to the time that the action statement is entered.
For example,15.3.0. A requires the unit to be placed in hot shutdown within seven hours and in cold shutdown within 37 j
hours.
In this case, a total of seven hours is allowed for reaching hot shutdown and a total of 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />, not 44 hours5.092593e-4 days <br />0.0122 hours <br />7.275132e-5 weeks <br />1.6742e-5 months <br />, is allowed for reaching cold shutdown from the time the action statement is entered.
If hot shutdown is reached in three hours, the time allowed for reaching cold shutdown is the next 34 hours3.935185e-4 days <br />0.00944 hours <br />5.621693e-5 weeks <br />1.2937e-5 months <br /> because the total time allowed for reaching cold shutdown is 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />.
1 15.3.0.A and 15.3.0.8 specify actions for conditions not covered in other specifications.
The requirements of 15.3.0.A and 15.3.0.B do not apply when a unit is in cold or refueling shutdown because the unit is already in the most restrictive plant condition required by 15.3.0.A or 15.3.0.B.
4 15.3.0.C establishes that, upon discovery that a Limiting Condition for Operation has been entered, the associated actions shall be performed.
The amount of time to complete each required action is applicable from the point in time that the action statement is entered. The required actions establish those measures that must be taken within specified times when the requirements of an LCO are not met. This specification establishes that:
Unit 1 - Amendment 50,152,163 15.3.0-3 Unit 2 - Amendment 55,155,167
1.
Completion of the required actions within the specified times constitutes compliance with a specification; and 2.
Completion of the required actions is not necessary when the requirements of an LCO are met within the specified amount of time, unless otherwise specified.
There are two basic types of required actions. The first type of action specifies a time limit in which the requirements of the LCO must be met. This is the amount of time to restore an inoperable system or component to operable status or to restore variables to within specified limits.
If this type of action is not completed within the specified time, a shutdown may be required to place the unit in a condition in which the specification is not applicable. The second type of action specifies the remedial measures that permit continued operation of the unit (s) that is not further restricted by the completion time.
Completing required actions is not necessary when the requirements of an LC0 are met or are no longer applicable, unless otherwise stated in the individual specification.
15.3.0.D delineates additional conditions which must be satisfied to permit operation to continue, consistent with the LC0 statements for power sources, when a normal or standby emergency power source is not operable.
It specifically prohibits operation when one system, subsystem, train, component, or device is inoperable because its normal or standby emergency power source is inoperable and a redundant system, subsystem, train, component, or device is inoperable for another reason.
The provisions of 15.3.0.D permit the action statements associated with individual systems, subsystems, trains, components, or devices to be consistent with the action statements of the associated electr,1 cal power source.
It allows operation to be governed by the time limits of the action statement associated with the LCO for the normal or standby emergency power source, not the individual action statements for each system, subsystem, train, component, or device determined to be inoperable solely because of the inoperability of its normal or standby emergency power source.
For example, Specification 15.3.7.B.I.f, g, and h allow a seven-day out-of-service time for the normal or standby emergency power source for the appropriate buses.
If l
the definition of operable were applied without consideration of 15.3.0.D, all j
systems, subsystems, trains, components, or devices supplied by the inoperable normal i
Unit 1 - Amendment 50,152,163 15.3.0-4 i
Unit 2 - Amendment 56d56,167
or standby emergency power source would also be inoperable. This would invoke the applicable action statements for each of the applicable LCOs. However, the provisions of 15.3.0.D permit the time limits for continued operation to be consistent with the statement for the inoperable normal or standby emergency power source instead, provided the other specified conditions are satisfied.
In this case all redundant systems, subsystems, trains, components, and devices must be operable, or otherwise satisfy 15.3.0.D (i.e., be capable of performing their design function and have at least one normal or one standby emergency power source operable).
If these conditions are not satisfied, shutdown is required in accordance with 15.3.0.A or 15.3.0.B.
In the cold and refueling shutdown conditions, 15.3.0.D is not applicable. Therefore, the individual action statements for e'ach applicable LC0 in these conditions must be followed.
15.3.0.E addresses the momentary loss of power to a component when prompt action is initiated resulting in reenergization from an alternate source, tripping the channel of logic, or initiating operator action as specified in Table 15.3.5-2.
Such a situation does not constitute an unsafe condition.
During the short period of the 4
corrective or required action, the operator is sensitive to the condition of the unit l,
and the possible effects of the logic systems, therefore the occurrence of such an event should not constitute a violation of the specification with respect to minimum operable channels.
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15.3.0.F establishes the allowance for restoring equipment to service when it has been removed from service or declared inoperable to comply with required actions.
The sole purpose of 15.3.0.F is to provide an exception to 15.3.0.C to allow the performance of 4
testing to demonstrate:
1.
The operability of the equipment being returned to service; or 2.
The operability of other equipment.
The amount of time that equipment is returned to service, in conflict with the requirements of the action statements, is limited to the time absolutely necessary to perform the allowable testing.
15.3.0.F does not provide time to perform any other preventive or corrective maintenance, i
Unit 1 - Amendment 50rM2,163 15.3.0-5 Unit 2 - Amendment 55,156,167
4 For example,15.3.0.F allows a containment isolation valve that has been closed, to
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comply with associated action statements, to be reopened to perform the required i
operability testing on the valve. Additionally, IS.3.0.F allows an inoperable instrument channel to be taken out of the tripped condition in order to permit the l
trip system logic to function and indicate the appropriate response during the performance of testing on another instrument channel in the same trip system.
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Unit 1 - Amendment 50r140,163 15.3.0-6 Unit 2 - Amendment 5&,-166,167
i a.
Four service water pumps are operable, two from each train.
b.
All necessary valves, interlocks and piping required for the
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functioning of the Service Water System during accident conditions are also operable.
1 2.
During power operation, the requirements of 15.3.3.D-1 may be modified to allow one of the following components to be inoperable at any one l
time.
If the system is not restored to meet the conditions of I
15.3.3.D-1 within the time period specified, both reactors will be placed in the hot shutdown condition within six hours and in cold
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shutdown within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
1 a.
One of the four required service water pumps may be out of service provided a pump is restored to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, i
b.
One of the two loop headers may be out of service for a period of 4
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
l c.
A valve or other passive component may be out of s'ervice provided repairs can be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
1 The normal procedure for starting the reactor is, first, to heat the reactor coolant to near operating temperature, by running the reactor coolant pumps.
The reactor is then made critical by withdrawing control rods and/or diluting boron in the coolant.m With this mode of start-up, the energy stored in the I
reactor coolant during the approach to criticality is substantially equal to that during power operation and therefore to be conservative most engineered safety system components and auxiliary cooling systems, shall be fully operable.
During low temperature physics tests there is a negligible amount of stored energy in the reactor coolant, therefore an accident comparable in severity to the Design Basis Accident is not possible, and the engineered safety systems are-not required.
1 Unit 1 - Amendment h 91,153,159,lS1,163 15.3.3-6
. Unit 2 - Amendment 3,95,157,153,155,167 i
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The operable status of the various systems and components is to be demonstrated by periodic tests, defined by Specification 15.4.5.
A large fraction of these tests will be performed while the reactor is operating in the power range.
If a j
component is found to be inoperable it will be possible in most cases to effect j
repairs and restore the system to full operability within a relatively short time.
j For a single component to be inoperable does not negate the ability of the system to perform its function, but it red :* ' S redundancy provided in the reactor design and thereby limits the ability u *
._:.ce additional equipment failures.
If it develops that (a) the inoperable component is not repaired within the specified allowable time period or (b) a second component in the same or related system is found to be inoperable, the reactor will initially be put in the hot shutdown condition to provide for reduction of the decay heat from the fuel, and l
consequent reduction of cooling requirements after a postulated loss-of-coolant I
accident. This will also permit improved access for repairs in some cases. After j
a limited time in hot shutdown, if the malfunction (s) are not corrected, the j
reactor will be placed in the cold shutdown condition, utilizing normal shutdown and cooldown procedures.
For example, specification 15.3.3. A.2.a allows one accumulator to be isolated or otherwise inoperable for periods of up to one hour, j
An inoperable accumulator may be defined as one with its outlet MOV shut, no pressure instrumentation operable, or water and/or nitrogen spaces cross-connected with the accumulator on the other loop.
If the inoperable accumulator is not l
restored within one hour then the conditions of section 15.3.0 apply which l
requires the affected unit, if critical, to be in hot shutdown within seven hours and in cold shutdown within 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br /> if the condition is not corrected.
In the f
cold shutdown condition there is no possibility of an accident that would release l
fission products or damage the fuel elements.
i The specified repair times do not apply to regularly scheduled maintenance of the engineered safety systems, which is normally to be performed during refueling shutdowns. The limiting times to repair are based on:
1)
Assuring with high reliability that the safety system will function properly if required to do so.
i 2)
Allowances of sufficient time to effect repairs using safe and proper l'
procedures.
d Unit 1 - Amendment M 8 d39,163 15.3.3-7 Unit 2 - Amendment 142,143,167
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