ML20005A724
| ML20005A724 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 06/24/1981 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20005A725 | List: |
| References | |
| TAC-43031, TAC-43032, NUDOCS 8107010069 | |
| Download: ML20005A724 (15) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION o
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O WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-266
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POINT BEACH NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 50 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 September 19, 1980, 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; e
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 Cornission'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 3.8 of Facility Operating License No. DPR-24 is hereby amended to read as follows-(B) Technical specifications The Technical Specifications contained in Appendices A and B,- as revised through Amendment No. 50, 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 it; issuance.
FOR THE NUCLEAR REGULATORY COMMISSION f
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' Robert A Clark, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: June 24, 1981 9
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UNITED STATES g
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%, *.. *,o WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-301 POINT BEACH NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 56 License No. DPR-27 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The apolication for amendment by Wisconsin Electric Power Company (the licensee) dated September 19, 1980, 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; 0.
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 latisfied.
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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 Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 56. are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This ifcense amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION D
k Rbbert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: June 24, 1981 i
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1 ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 50 TO FACILITY OPERATING LICENSE NO. DPR-24 AMENDMENT-NO. 56 TO FACILITY OPERATING LICENSE NO. DPR-27 DOCKET NOS. 50-266 AND 50-301 Revise Appendix A as follows:
Remove Pages Insert Pages 15-i' 15-1 15.1-2 15.1-2 15.3.0-1 15.3.0-2 15.3.0-3 15.3.0-4 15.3.0-5 15.6.4/5-1 15.6.4/5-1 (overleaf) 15.6.5-2 15.6.5-2 15.6.11-1 15.6.11-1 l
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TABLE OF CONTENTS Section Title Page 15 TECHNICAL SPECIFICATIONS AND BASES 15.1 Definitions 15.1-1 15.2.0 Safety Limits and Limiting Safety System Settings 15.2.1-1 15.2.1 Safety Limit, Reactor Core 15.2.1-1 15.2.2 Safety Limit, Reactor Coolant System Pressure 15.2.2-1 15.2.3 Limiting Safety System Settings, Protective Instrumentation 15.2.3-1 15.3 Limiting Conditions for Operation 15.3-0 15.3.0 General Considerations 15.3.0-1 15.3.1 Reactor Coolant System 15.3.1-1 15.3.2 Chemical and Volume Control System 15.3.2-1 15.3.3 Emergency Core Cooling System, Auxiliary Cooling Systems, Air Recirculation Fan Coolers, and containment Spray 15.3.3-1 15.3.4 Steam and Power Conversion System 15.3.4-1 15.3.5 Instrumentation System 15.3.5-1 15.3.6-1 15.3.6 Containment System 15.3.7-1 15.3.7 Auxiliary Electrical Syste=s 15.3.8 Refueling 15.3.'-1 15.3.9 Effluent Releases 15.3.9-1 15.3.10 Control Rod and Power Distribution Limits 15.3.10-1 15.3.11 Movable In-Core Instrumentation 15.3.11-1 15.3.12 Control Room Smergency Filtration 15.3.12-1 15.3.13 Shock Suppressors (Snubbers) 15.3.13-1 15.3.14 Fire Protection System 15.3.14-1 15.3.15 Overpressure Mitigating System 15.3.15-1 15.3.16 Reactor Coolant System Pressure Isolation Valves 15.3.16-1 15.4 Surveillance Requirements 15.4-1 15.4.1 Operational Safety Review 15. 4 ~.1-1 15.4.2 In-Service Inspection of Pri=ary S,. stem Components 15.4.2-1 15.4.3 Primary System Testing Following Opening 15.4.3-1 15:4-4 Containment Tests 15.4.4-1 15.4.5 Emergency Core Cooling System and Containment Cooling System Tests 15.4.5-1 15.4.6 Emergency Power System Periodic Tests 15.4.6-1 15.4.7 Main Steam Stop Valves 15.4.7-1 15.4.8 Auxiliary Feedwater System 15.4.8-1 15.4.9 Reactivity Anomalies 15.4.9-1 15.4.10 Operational Environmental Monitoring 15.4.10-1 15.4.11 Control Room Emergency Filtration 15.4.11-1 15.4.12 Miscellaneous Radioactive Materials Sources 15.4.12-1 15.4.13 Shock Suppressors (Snubbers) 15.4.13-1 15.4.14 Surveillance of Auxiliary Building Crane 15.4.14-1 15.4.15 Fire Protection System 15.4.15-1 15.4.16 Reactor Coolant System Pressure Isolation Valves Leakage Tests 15.4.16-1 15-1 Unit 1 - Olddf Apffl 20/ 1981. 50 Unit 2 - Olddf Ap/II 204 1981, 56
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'Ouadrant Power Tilt' Quadrant to average power tilt is expressed in percent as defined by,the following squation:
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'aversse for all quadrants c.
Operability A system,~ subsystem, train, component, o'r device shal1 }e operable or have operability when:it.is capable of performing its function (s) as ImplicitJ n this definition i
analyzed in the safety analysis report.
is the assumption.that 'necessary instrumentation, controls, normal and~ emergency _ electrical power sources, cooling or seal water, lubrication or other auxiliary equipment-required.for the system,
- subsystem, train, component or device to perform its function (s) are capable of performing their related support fun,c tion (s).
d.
Containment Integrity *
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Containment integrity is defined to exist when:
- 1) All non-automatic containment isolation valves and blind flanges are closed as required.
- 2) The equipment hatch is properly closed.
- 3) At least one door in each personnel air lock is properly closed.
- 4) All automatic containment isoldtion valves are operable or are secured closed.
- 5) The uticontrolled containment leakage satisfies Specification 15.4.4.
e.
Protective Instrumentation Logic 4
- 1) Analog Channel An analog channel is an arrangement of components and modules as required to generate a single protective action signal when required by a plant condition. An analog channel loses its identity where single action signals are combined.
- Containment isolatJon valves are discussed in FFDSAR Section 5.2.
Unit 1 - Amendment No. 43, 50 Unit 2 -' Amendment No. 48, 56 15.1-2
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. 15.31 Limitina Conditions-for Operation 15.3.0 General Considerations A. 'Many of the Limiting Conditions for Operation.(LCO)' presented in these specifications provide a temporary relaxation of the singis failure criterion, consistent with overall reliability considerations, to allow time periods during which corrective
- I action may-be taken to restore the system to. full operability.
If the situation has not been corrected within the specified time period, and the LCO prescribes no other specific action, Ean affected unit, which is critical. shall.be placed in the.
' hot shutdown condition within three hours..In the-event an LCO cannot be satisfied because of equipment failures or-limitations beyond.those specified in the permissible condi-tions of the LCO,.the affected unit, which is critical, shall be placed in the hot shutdown condition'within three hours of discovery of the situation.
B.
If the conditions which prompted the shutdown required by 15.3.0.A cannot be corrected, many LCOs specify an additional
. time period until the unit must be placed in the cold shutdown condition.
If no such time period is specified, the unit shall be put into the cold ghutdown condition within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of discovering the situation.
C.
When a system, subsystem, train, component or device is deter-mined to be inoperable solely because its emergency power source is' inoperable, or solely because its normal. power source is inoperable, the system, subsystem, train, component or device may be considered operable for the purpose of satisfying the requirements of the applicable Limiting Condi-tion for Operation, provided:
(1) the alternate power. source (normal or emergency) is operable and (2) all redundant system (s),
subsystem (s), train (s), component (s) and device (s) are operable.
15.3.0-1 Unit 1 - Amendment No. 50 Unit 2 - Amendment No. 56 6'
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If either condition (1) or (2) cannot be met, specifica-tions 15.3.0.A and 15.3.0.B become applicable. This'specifica-tion is not applicable during cold shutdown or refueling shut-down conditions..
D.
A momentary loss of normal or emergency-power resulting in immediate corrective or required action in accordance with Table 15.3.5-2, i.a.., 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 minimum operable channels or minimum degree of redundancy, unless said loss is the result of operator error or procedural violation.
Bases Specifications 15.3.0.A and 15.3.0.3. delineate the action to be taken for circu= stances not directly provided for in the action statements of the LCO and whose occurrence would violate the intent of the specification.
For example, Specification 15.3.3.A.2.e permits a single Reactor Coolant System accumulator to be isolated for up to one hour during power opera-tions. Under the terms of Specificatbns,15.3.0.A and 15.3.0.B, if more than one accumulator is isolated or inoperable, the unit is required to be in hot shutdown within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> of discovery of the condition and in the cold shutdown condition within the following 45 hours5.208333e-4 days <br />0.0125 hours <br />7.440476e-5 weeks <br />1.71225e-5 months <br /> unless corrective measures are completed. As a tarther example, Specification 15.3.3.B.2.b permits one Containment Spray Pump to be out-of-service for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during power operations. Under the terms of these Specifications, if both of the required Containment Spray Pumps are inoperable, the unit is required to be in hot shutdown within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, and in the cold shutdown condition within the next 45 hours5.208333e-4 days <br />0.0125 hours <br />7.440476e-5 weeks <br />1.71225e-5 months <br />.
It is assumed the unit is brought to the required condition within the required times by promptly initiating and carrying out the appropriate statement.
15.3.0-2 Unit 1 - Amendment No. 50 Unit 2 - Amendment No. 56 O
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Y Specification 15.3.0.C delineates additional conditions which must be satisfied to permit operation to continue, consistent with the Limiting Condition for Operation statements for power sources, when a normal or emergency power source is not operable.
It specifically prohibits opera-tion when one system, subsystem, train, component or device-is inoperable because its normal or emergency power source is inoperable and a' redundant system, subsystem, train, component or device is Inoperable for another reason.
The provisions of this specification permit the action statements associated with-individual systems, subsystems, trains,' components, or devices to be consistent with the action statements of the associated electrical power source.
It allows operation to be governed by the time limits of.the action statement associated with the Limiting Condition for Operation for the normal or emergency power source, not the individual
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action statements for each system, subsystem, train, component or device determined to be inoperable solely because of the inoperability of its normal or emergency power source.
For example, Specification 15.3.7.A.l.e allows a 7 day out-of-service time for one emergency diesel generator.
If the definition of operable were applied without consideration of Specification 15.3.0.C, all systems, subsystems, trains, components or devices supplied by the inoperable emergency power source would also be inorerable. This would invoke the applicable action statements for each of the applicable Limiting Conditions for Operation. However, the provisions of Specification'15.3.0.C permit the time limits for continued operation to be consistent with the statement for the inoperable emergency diesel generator instead, provided the other specified conditions are satisfied.
In this case, the corresponding normal power source must be operable, and all redundant systems, subsystems, trains, components, and devices must be operable, or otherwise satisfy Specification 15.3.0.C (i.e., be capable of performing their design function and have at least one normal or one energency power source operable).
If these conditions are not satisfied, shutdown is required in accordance with Specification 15.3.0.A.
15.3.0-3 Unit 1 - Amendment No. 50 Unit 2 - Amendment No. 56 e.
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- tc As'a'further. example, Specification 15.3.7.A.l.d requires in parts
- that 4160 volt buses A03 and A04 be energized for the unit to be taken-4 J critical.. - Specification'15.3.7.B.1.d permits either bus A03' or A04 to be taken out-of-service for up to.7 days provided both diesel generators are operable and the associated diesel generator.is operating and provid-7 ing power to the engineered safeguard bus normally supplied by the out-of-service bus.
If the' definition of' operable were applied without considera-tion of Specification 15.3.0.C all systems,. subsystems,' trains, components and devices supplied by the inoperable normal power sources- (i.e., the out-of-service.. bus A03 or A04) would also be inoperable. This would invoke the' applicable action statements for each of the applicable LCOs. However, the provisions of this Specification 15.3.0.C permit the time limit for continued operation to be consistent with the action statement for the inoperable normal power source, in this ' case 7 days, provided the other specified conditions are satisfied. These conditions are that for the engineered safeguards systems on one bus the emergency power source must be operable (as -must be' the components supplied by the emergency power source)'and all redundant systems, subsystems, trains, components and 4
devices-in the other engineered safeguards systems.must be operable, or likewise satisfy Specification.15.3.0.C. (i.e., be capable of performing-a their design function and.have an emergency power source operable).
In other words, both emergency power sources must be operable and all redundant systems, subsystems, trains, components and devices in both divisions of
- engineered safeguards systems must also be operable.
If~these conditions are not satisfied, shutdown is required in accordance with this specffica-tion.
In the cold shutdown and refueling shutdown conditions, Specification 15.3.0.C is not applicable, and thus the individual action statements for each applicable Limiting Condition for Operation in these conditions must 4
be adhered to.
Specification 15.3.0.D addresses the momentary loss of power to a component when immediate 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
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not constitute an unsafe, condition. During the short period of the
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corrective or required action, the operator is sensitive to the condition of the unit 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 or minimum degree
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'15.6.4 TRAINING 15.6.4.1 A retraining and' replacement training program for the facility staff shall be maintained under the direction of the Training Supervisor and shall meet or exceed the requirements and recommendations of.Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.-
15.6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Fire Protection Supervisor and shall meet or exceed the requirements of Section 27 of the NFPA Code-1976, except that the' meeting frequency may be quarterly.-
15.6.5 REVIEW AND AUDIT 15.6.5.1 Raty and Call Superintendents a.
To assist and counsel the Shift Supervisor in case of significant operating events, a Duty and Call Superintendent l-Group has been established. The Duty and Call Superinten-dent. Group shall consist of any' qualified person designated by the Manager - Nuclear Operations.
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b.
In the event of a reporqable occurrence, the Shift Super-l visor shall communicate with at least one Duty and Call l
Superintendent before taking other than the immediate on-i the-spot action required. One Duty and Call Superintendent will be assigned to be "on call" at all times. The Duty l
and Call Superintendent provides continuously available counsel, call out backups, and review to the Shift Super-Visor.
15.6.5.2 Manager's Supervisory Staff FUNCTION 15.6.5.2.1 The Manager's Supervisory Staff (MSS) shall function to advise the Manager - Nuclear Operations on all iatters related to nuclear safety.
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.,7 COMPOSITION 15.6.5.2.2 The Manager's Supervisory Staff shall be composed of the:
Chairman: Manager - Nuclear Operations
' Member:
Superintendent - Operations Member:
Superintendent - Maintenance & Construction
. Member:
Instrument and Control Engineer Member:
Superintendent - Technical Services Member:
Radiochemical. Engineer Member:
Health Physicist Member:
Assistant to the Manager --Nuclear Operations Member:
Beactor Engineer ALTERNATES 15.6.5.2.3 Alternate members shall be appointed in writing by the MSS Chairman to serve on a temporary basis; however, no more than two alternates shall participate in MSS activities at any one time.
MEETING FREQUENCY 15.6.5.2.4 The MSS shall meet at least once per calendar month and as l
convened by the MSS Chairman.
l OUORUM 15.6.5.2.5 A quorum of the MSS shall consist of the Chairman and four members iacluding alternates.
l RESPONSIBILITIES 15.6.5.2.6 The Manager's Supervisory Staff shall:
a) Review exist.tng and propcsed normal, abnormal end I
emergency-operating procedures. Review maintenance procedures and proposed changes to these procedures i
and other procedures or changes thereto as determined l
by the Manager to affect plant operational safety.
(Re: Section 15.6.7 for area of review.)
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15.6.11 RADIATION PROTECTION PROGRAM Specification Radiological control procedures shall be written and made available to all station personnel, and shall state permissible radiation exposure levels.
The radiation protection program shall meet the requirements of 10 CFR 20, with the exception of the following:
Paragraph 20.203 - Caution signs, labels and signals In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 mRam/hr but less than 1000 mrem /hr shall be barricaded and conspicucusly posted as a high radiation area and entrance thereto shall be centrolled by requiring issuance of a Radiation Work Permit
- as described in Point Beach Nuclear Plant Health Physics Administrative Control Policias and Procedures Manual, Section 2.7.
Any individual or group of individuals permitted to enter such areas shall be provided with at least one of the following:
a.
A radiation monitoring device which cortinuously indicates the radiation dose rate in che area, b.
A radiation monitccing device which continuously integrates the radiation dose rate in the area and alarms when a preset inte-grated dose is received.
Entry into such areas with this mealtoring device may be made after the dose rate level in the area has been established and personnel have been made knowledge-able of these conditions, Coverage by an individual qualified in radiation protection pro-c.
cedures who is equipped with a radiation dose rate monitoring device. This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance as specified by the facility Health Physics Supervisor on the Radiation Work Permit.
The requirements above shall also apply to each high radiation area in which the intensity or radiation is greater than 100 mrem /hr.
In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control of the Duty Shif t Supervisor and the plant Health Physicist.
- Health Physics qualified personnel or personnel escorted by Health Physics personnel shall be exempt from the Radiation Work Permit issuance requirement during the performance of their assigned radiation protection duties, provided thef comply with approved radiation protection procedures as they relate to entry into high radiation areas.
15.6.11-l Unit 1 - Amendment No. 50 Unit 2 - Amendment No. 56 8
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