ML19332B091
| ML19332B091 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 09/19/1980 |
| From: | WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML19332B090 | List: |
| References | |
| TAC-43031, TAC-43032, NUDOCS 8009250253 | |
| Download: ML19332B091 (8) | |
Text
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b.
Quadrant Power Tilt Quatrant to average power tilt is expressed in percent as defined by the following equation:
power in any core quadrant -1 100 x average for all quadrants c.
Operability A system, subsystem, train, component, or device shall be operable or have operability when it is capable of performing its function (s) as analyzed in the safety analysis report.
Implicit in this definition 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 function (s),
d.
Containment Integrity
- Containment integrit" *s defined to exist when:
)
1)
All non-automatic containment isolation valves and blind i
flanges are closed as required.
- 2) The equipment hatch is properly closed.
- 3) At least one door in each personne" air lock is properly closed.
- 4) All automatic containment isolation valves are operable or are secured closed.
- 5) The uncontrolled containment leakage satisfies Specification 15.4.4.
e.
Protective Instrumentation Logic
- 1) Analog Channel An analog channel is an arrangement of components and modules as required to generate a single protective action signal when 0253 15.1-2 400925
15.3 Limiting Conditions for Operation 15.3.0 General Considerations A.
Many of the Limiting Conditions for Operation (LCO) presented in these specifications provide modification of the conditions of the LCO to allow time periods during which corrective action may be taken to restore the system to full operability.
If the situation has not been corrected *:1Lhin the specified time period, and the LCO prescribes no other specific action, an 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 l
limitations beyond those specified in the permissible conditions 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 condition which allows operation of the residual heat removal system with-in 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of reaching hot shutdown.
C.
When a system, subsystem, train, component or device is determined to be inoperable solely because its emergency power source is inoperable, or solely because its normal power source is inoperable, the system, subsystem, train, 2
component or device may be censidered operable for the i
purpose of satisfying the requirements of the applicable Limiting Condition for Operation, provided:
15.3.0-1
(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.
If either condition (1) or (2) cannot be met, specifications 15.3.0.A r.nd 15.3.0.B become applicable. This specification is not applicable during cold : shutdown or refueling shutdown conditions.
D.
A momentary loss of normal cc emergency power resulting in immediate corrective or required action in accordance with Table 15.3.5-2, i.e., placing associated Channels into the trip condition or shutdown of the unit, shall not be inter-preted as causing a violation of the specification with respect to minimum operable channels or minimum degree of redundancy.
15.3.0-2
Bases Specifications 15.3.0.A and 15.3.0.B delineate the action to be taken for circumstances 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 operations. Under the terms of Specification 15.3.0. A, 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 conditi,n and in a condition to pereit operation of the residual heat removal system within the following 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> unless corrective measures are completed.
As a further 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 />, l
and in a condition to permit operation of the residual heat removal system in the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
It is assumed the unit is brought to the required condition
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within the required times by promptly initiating and carrying out the appropriate statement.
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 operation when one system, subsystem, train, component or device is inoperable because its normal or emer-gency 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 statum?nts associated with individual systems, subsystems, trains, components, or devices to be consis-tent with the action statements of the associated alectrical power source.
It allows operation to be governed by the time limits of the action statement associ-ated with the Limiting Condition for Operation for the normal or emergency power 15.3.0-3
source, not the' individual action statements for each system, subsystem, train, component or device determined to be inoperable solely because of the inoper-ability of its normal or. emergency power source.
For example, Specification 15.3.7. A.l.e allows a 7 -day out-of-sarvice time
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If the definition of operable were applied for one emergency dicesl generator.
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 inoperable. This would invoke the applicable action statements for each I
- of the applicable Limiting Conditions for Operation. However, the provisions of
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Specification 15.3.0.C permit the time 10mits for continued operation to be
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l consistent with the statement for the inoperable emergency diesel generator instead, 4
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provided the other specified conditions are satisfied.
In Mtis case, the correspond-J-
i ing normal power source must be operable, and all redundant systems, subsystems, trains, components, and devices must be operable, or otnerwise satisfy Specification 15.3.0.C (i.e., be ' capable of performing their design function and have at least one normal or one emergency power source operable).
If these conditions are not satisfied, shutdown is required in accordance with Specification 15.3.0.A.
As:a further example, specification 15.3.7.A.l.d requires in parts that 4160 4
volt buses A03 and A04 be energized for the unit to be taken critical. Specifi-I cation 15.3.7.B.l.d permits either bus A03 or A04 to be out-of-service for up to 7 days provided both diesel generators are operable and the associated diesel generator is operating and providing power to the engineered safeguard bus i
normally supplied by. the out-of-service bus.
If the. definition of operable were applied without' consideration 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 oor 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 1
15.3.0-4 x
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operation to be consistent with the action statement for the inoperable normal power source, in this case 7 days, provided the other specified conditions 4
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, i*
trains, components and devices in the other engineered safeguards systems must i
be operable, or likewise satisfy Specification 15.3.0.C (i.e., be capable of performing 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, y
shutdown is required in accordance with this specification.
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 be adhered to.
Specification 15.3.0.D addresses the momentary loss of power to a component when immediate action is initiated resulting in reenergi ation frem 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 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 of redundancy.
15.3.0-5
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COMPOSITION 15.6.5.2.2 The Manager's Supervisory Staff shall be composed of ther Chairman: Manager - Nuclear Operations Member:
Superintendent - Operations.
Member:
Superintendent - Maintenance & Construction Member:
Instrument and Control Engineer Member:
Superintendent - Technical Services
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,e Member Radiochemical' Engineer Member Health Physicist Member:
Assistant to the Manager
, Nuclear Operations Member:
Reactor Engineer ALTERNATES 15.6.5.2.3 Alternate members shall be appointed in writing by the MSS Chairman to serve on a temporary basist howeves, no more than two alternates shall participate in MSS activities at any one time.
MEETING FRIQUENCY 15.6.5.2.4 The MSS shall meet at least once per calendar month and as convened by the MSS Chairman.
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QUORUM j
15.6.5.2.5 A quorum of the MSS shall consist of the Chairman and four mem-
'bers including alternates.
RESPONSIBILITIES 15.6.5.2.6 The Manager's Supervisory Staff shall:
a) Review existing and proposed normal, abnormal and emergency operating proceduras.
Review maintenance procedures and proposed changes :o these procedures and other procedures or changes thereto as determined by the Manager to affect plant operational safety.
(Re Section 15.6.7 for area of review.)
O 15.6.5-2
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15.6.11 RADIATION PROTECTION PROGRAM Specification Radiological centrol 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 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit
- as described in Point Beach Nuclear Plant Health Physics Administrative Control Policies 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 continuously indicates the radiation dose rate in the area.
b.
A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate level in the area has been estab-lished and personnel have been made knowledgeable of these conditions.
c.
Coverage by an individual qualified in radiation protection pro-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 1000 mrem /hr.
In addition, locked doors shall be provided to prevent unauthorized entry into such areas and ' he keys shall be maintained under the administrative control of the Cuty F1. Aft Supervisor and the plant Health Physicist.
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- 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 radia: ion protection duties, provided they comply with approved radiation protection procedures as they relate to entry into high radiation areas.
15.6.11-1
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