ML20216H363
| ML20216H363 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 04/15/1998 |
| From: | Brinkman D NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20216H368 | List: |
| References | |
| NUDOCS 9804210120 | |
| Download: ML20216H363 (3) | |
Text
r
~
' pt** 44g g
i UNITED STATES
}
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 208 2 4001 DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY
{
PENNSYLVANIA POWER COMPANY l
l DOCKET NO. 50-334 BEAVER VALLEY POWER STATION. UNIT NO.1 l
l AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.213 l
License No. DPR-66 l
l 1.
The Nuclear Regulatory Commission (the Commission) has found that:
l A.
The appli' in for amendment by Duquesne Light Company, et al. (the iicensee) dated M
.16,1998, complies with the standards and requirements of the Atomic Energy Ac. 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 (i) that the activities authorized by this amendment l
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; j
D.
The issuance of this amendment will not be inimical to the common defense and I
security or to the health and safety of the public; and i
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and eli applicable requirements have been satisfied.
l l
I 9804210120 980415 PDR ADOCK 05000334 P
PDR h
'.o l
2 2.
Accordingly, the license is amended by changes to the Technical Specifications as l
indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-66 is hereby amended to read as follows:
(2) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 213 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, to be implemented within 30 days, r
FOR THE NUCLEAR REGULATORY COMMISSION l
Robert A. Capra, Director Project Directorate 1-2 Division of Reactor Projects. l/II Office of Nuclear Reactor Regulation i
Attachment:
Changes to the Technical l
Specifications Date ofissuance: April 15, 1998 i
l l
l l
l
e l
l l
ATTACHMENT TO LICENSE AMENDMENT NO. 213 1
FACILITY OPERATING LICENSE NO. DPR-66 DOCKET NO. 50-33.4 Replace the following pages of Appendix A Technical Specifications, with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines l
indicating the areas of change.
Remove Insert l
3/4 0-2 3/4 0-2 i
B 3/4 0-5 B 3/4 0-5 B 3/4 0-6 B 3/4 0-6 8 3/4 0-7 8 3/4 0-7 B 3/4 0-8 B 3/4 0-8 B 3/4 0-9
(
\\
i l
l l
i l
l l
l DPR-66 3/4.O APPLICABILITY l
LIMITING CONDITION FOR OPERATION (continued) l i
1.
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 />, t
2.
At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and 3.
At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
This specification is not applicable in MODES 5 or 6.
i 3.0.6 Equipment removed from service or declared inoperable to l
comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment.
This is an exception to Limiting Condition for Operation 3.0.1~ for the system-returned to service under administrative control to perform the l
testing required to demonstrate OPERABILITY.
(
1 1
1 SURVEILLANCE REQUIREMENTS i
4.0.1 Surveillance Requirements shall be met during the l
OPERATIONAL MODES or other conditions specified for individual l
Limiting conditions for Operation unless otherwise stated in an i
individual Surveillance Requirement.
l l
4.0.2 Each Surveillance Requirement shall be performed within the I
specified time interval with a maximum allowable extension not to j
exceed 25% of the surveillance interval.
4.0.3 Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by Specification 4.0.2, shall l
l constitute noncompliance with the OPERABILITY requirements for a i
Limiting Condition for Operation.
The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed.
The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit the completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Surveillance Requirements do not have to be performed on inoperable equipment.
4.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made unless the Surveillance Requirement (s) associated with a Lin:iting Condition for Operation has been performed within the stated surveillance interval or as otherwise specified.
This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements.
4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2 and 3 components shall be applicable as follows:
a.1 Inservice inspection of ASME Code Class 1,
2 and 3 components shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g).
BEAVER VALLEY - UNIT 1 3/4 0-2 Amendment No. 213
DPR APPLICABILITY
{
l i
l BASES components and devices in the other division must be OPERABLE, or l
likewise satisfy Specification 3.0.5 (i.e., be capable of performing their design functions and have an emergency power source OPERABLE).
In other words, both emergency power sources must be OPERABLE and all redundant systems, subsystems, trairs, components and devices in both j
divisions must also be OPERABLE.
If these conditions are not
(
satisfied, action is required in accordance with this specification.
l l
In MODES 5 or 6 Specification 3.0.5 is not applicable, and thus the individual ACTION statements for each applicable Limiting Condition
'for Operation in these MODES must be adhered to.
~
Snecification 3.0.6 establishes the allowance for restoring equipment to service under administrative controls when it has been removed l
from service or declared inoperable to comply with ACTIONS.
The sole purpose of this specification is to provide an exception to specification 3.0.1 (e.g., to not comply with the applicable ACTIONS) to allow the performance of Surveillance Requirements and post maintenance testing to demonstrate:
The OPERABILITY of the equipment being returned to service; a.
or I
b.
The OPERABILITY of other equipment.
The administrative controls ensure the time the equipment is returned l
to service in conflict with the requirements of the \\CTIONS is limited to the time absolutely necessary to perform the allowed testing.
This specification does not provide time to perform any l
other preventive or corrective maintenance.
Minor corrections such as adjustments of limit switches to correct position indication anomalies are considered within the scope of this specification.
Other more significant tasks such as valve packing replacement are not permitted by this specification.
l It is expected that the testing will confirm equipment operability.
Should the testing demonstrate that the equipment is not operable, the provisions of LCO 3.0.1 will be applied.
An example of demonstrating the OPERABILITY of the equipment being l
returned to service is reopening a containment isolation valve that i
has been closed to comply with ACTIONS and must be reopened to perform the surveillance requirements.
BEAVER VALLEY - UNIT 1 B 3/4 0-5 Amendment No. 213 t
DPR-66 APPLICABILITY I
BASES l
An example of demonstrating the OPERABILITY of other equipment is taking an inoperable channel or trip system out of the tripped condition to' prevent the trip function from occurring during the performance of a surveillance requirement on another channel in the other trip system.
A similar example of demonstrating the OPERABILITY of other equipment is taking an inoperable channel or trip system out of the tripped condition to permit the logic to function and indicate the appropriate response during the performance of a surveillance requirement on another channel in the same trip system.
Soecification 4.0.1 throuah 4.0.5 establish the general requirements applicable to surveillance Requirements.
These requirements are based on the Surveillance Requirements stated in the Code of Federal Regulations,10 CFR 50.36(c) (3) :
" Surveillance requirements are requirements relating to test, calibration, or inspection to ensure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions of operation will be met."
Soecification 4.0.1 establishes the requirement that surveillances must be performed during the OPERATIONAL MODES or other conditions for which the requirements of the Limiting conditions for Operation apply unless otherwise stated in an individual Surveillance Requirement.
The purpose of this specification is to ensure that surveillances are performed to verify the operational status of systems and components and that parameters are within specified limits to ensure safe operation of the facility when the plant is in a MODE or other specified condition for which the associated Limiting conditions for Operation are applicable.
Surveillance Requireme its do not have to be performed when the facility is in an OPERATIONAL MODE for which the requirements of the associated Limiting Condition for Operation do not apply unless otherwise specified.
The Surveillance Requirements associated with a Special Test Exception are only applicable when the Special Test Exception is used as an allowable exception to the requirements of a Specification.
Snecification 4.0.2 establishes the limit for which the specified time interval for Surveillance Requirements may be extended.
It permits an allowable extension of the normal surveillance interval to facilitate surveillance scheduling, and consideration of plant operating conditions that may not be suitable for conducting the surveillance; e.g.,
transient conditions or other ongoing surveillance or maintenance activities.
It also provides flexibility to accommodate the length of a fuel cycle for surveillances that are performed at each refueling outage and are specified with an 18-month BEAVER VALLEY - UNIT 1 B 3/4 0-6 Amendment No. 213
- DPR-66 APPLICABILITY BASES surveillance interval.
It is not intended that this provision be used repeatedly as a convenience to extend surveillance intervals beyond that specified for surveillances that are not performed during refueling outages.
The limitation of Specification 4.0.2 is based on engineering j2dgement and the recognition that the most probable result of a1y particular surveillance being performed is the verification c.t conformance with the Surveillance Requirements.
This provision is mufficient to ensure that the reliability ensured
,through surveillance activities is not significantly degraded beyond that obtained from the specified surveillance interval.
I
- gascification 4.0;3' establishes'the' failure to perform a'Surve'illance l
Requirement within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, as a condition that constitutes a failure to meet the OPERABILITY requirements for a Limiting Condition for Operation.
Under provisions of this specification, systems and components are assumed to be OPERABLE when Surveillance Requirements have been satisfactorily performed within the specified time interval.
However, nothing in this provision is to be construed as implying that systems or components are OPERABLE when they are found or known to be inoperable although still meeting the Surveillance Requirements.
This specification also clarifies that the ACTION requirements are applicable when Surveillance Requirements have not been completed within the allowed surveillance interval and that the time limits of the ACTION requirements apply from the point in time it is identified that a surveillance has not been performed and not at the time that the allowed surveillance interval was exceeded.
Completion of the Surveillance Requirement within the allowable outage time limits of the ACTION requirements restores compliance with the requirements of Specification 4.0.3.
However, this does not
, negate the fact that the failure to have performed the surveillance within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, was a
violation of the OPERABILITY requirements of a Limiting Condition for Operation that is subject to enforcement action.
Further, the failure to perform a surveillance within the provisions of Specification 4.0.2 is a violation of a Technical Specification requirement and is, therefore, a reportable event under the requirements of 10 CFR 50.73(a) (2)(i) (B) because it is a condition prohibited by the plant's Technical Specifications.
If the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or a shutdown is required to comply with ACTION requirements, e.g.,
Specification 3.0.3, a
24-hour allowance is provided to permit a delay in implementing the ACTION requirements.
l.
This provides an adequate time limit to complete Surveillance Requirements that have not been performed.
The purpose of this allowance is to permit the completion of a surveillance before a shutdown is required to comply with ACTION requirements or before BEAVER VALLEY - UNIT 1 B 3/4 0-7 Amendment No.213
I DPR-66 APPLICABILITY BASES other remedial measures would be required that may preclude completion of a surveillance.
The basis for this allowance includes consideration for plant conditions, adequate planning, availability i
l of personnel, the time required to perform the surveillance, and the l
safety significance of the delay in completing the required surveillance.
This provision also provides a time limit for the completion of Surveillance Requirements that become applicable as a l
consequence of MODE changes imposed by ACTION requirements and for l
completing Surveillance Requirements that are applicable when an l
exception to the requirements of Specification 4.0.4.is allowed.
If.
I a surveillance is not completed within the 24-hour allowance, the time limits of the ACTION requirements are applicable at that time.
When a surveillance is performed within the 24-hour allowance and the Surveillance Requirements are not met, the time limits of the ACTION l
requirements are applicable at the time that the surveillance is i
terminated.
i Surveillance Requirements do not have to be performed on inoperable equipment because the ACTION requirements define the remedial measures that apply.
However, the Surveillance Requirements have to be met to demonstrate that inoperable equipment has been restored to OPERABLE status.
Snecification 4.0.4 establishes the requirement that all applicable surveillances must be met before entry into an OPERATIONAL MODE or other condition of operation specified in the Applicability statement.
The purpose of this specification is to ensure that system and component OPERABILITY requirements or parameter limits are met before entry into a MODE or condition for which these systems and components ensure safe operation of the facility.
This provision applies to changes in OPERATIONAL MODES or other specified conditions associated with plant shutdown as well as startup.
Under the provisions of this specification, the applicable Surveillance Requirements must be performed within the specified surveillance interval to ensure that the Limiting Conditions for Operation are met during initial plant startup or following a plant outage.
When a shutdown is required to comply with ACTION requirements, the provisions of Specification 4.0.4 do not apply because this would delay placing the facility in a lower MODE of operation.
BEAVER VALLEY - UNIT 1 B 3/4 0-8 Amendment No. 213
l DPR-66 APPLICABILITY BASES soecification 4.0.5 establishes the requirement that inservice inspection of ASME Code Class 1,
2, and 3 components and inservice testing of ASME Code Class 1,
2, and 3 pumps and valves shall be performed in accordance with a periodically updated version of Section XI of the ASME Boiler and Pressure Vessel Code and Addenda as required by 10 CFR 50.55a.
These requirements apply except when relief has been provided in writing by the Commission.
This Specification includes a clarification of the frequencies for performing the incorvice inspection and testing. activities required i
by Section XI of the ASME Boiler and Pressure Vessel Code and applicable
?.ddenda.
This clarification is provided to ensure consistency in surveillance intervals throughout the Technical Specifications and to remove any ambiguities relative to the frequencies for performing the required inservice inspection and testing activities.
)
i Under the terms of this specification, the more.. restrictive requirements of the Technical Specifications take precedence over the j
ASME Boiler and Pressure Vessel Code and applicable Addenda.
The d
requirements of Specification 4.0.4 to perform surveillance activities before entry into an OPERATIONAL MODE or other specified condition takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows pumps and valves to be tested up,to one
{
week after return to normal operation.
The Technical Specification i
definition of OPERABLE does not allow a grace period before a f
component, that is not capable of performing its specified function, J
is declared inoperable and takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows a valve to be incapable of performing its specified function for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before being declared inoperable.
I BEAVER VALLEY - UNIT 1 B 3/4 0-9 Amendment No. 213
' i#'"%
[
+4 UNITED STATES j
NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 3rde6-W1 s.,*****/
DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY l
THE CLEVELAND ELECTRIC ILLUMINATING COMPANY l
THE TOLEDO EDISON COMPANY l
DOCKET NO. 50-412 BEAVER VALLEY POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 90 License No. NPF-73 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Duquesne Light Company, et al. (the licensee) dated March 16,1998, 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 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. NPF-73 is heraby amended to read as follows-(2) Technical Soecifications i
The Technical Specifications cc : elned in Appendix A, as revised through Amendment No. 90, and the Ei.e nmental Protection Plan contained in
)
Appendix B, both of which are attacned hereto are hereby incorporated in the license. DLCO shall operate the facility in accordance with the Technical i
Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance, to be implemented j
within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION Y'
Robert A. Capra, Director Project Directorate 12 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: April 15,1998 l
I l
l
I ATTACHMENT TO LICENSE AMENDMENT NO.on l
FACILITY OPERATING LICENSE NO. NPF-73 DOCKET NO. 50-412 l
4 Replace the following pages of Appendix A, Technical Specifications, with the enclosed pages as indicated. The revised pages are identified by amendment number and contain verticallines l
indicating the areas of change.
Remove Insert 3/4 0-2~
3/4 0-2 3/4 0-3 3/4 0 3 l
B 3/4 0-5 B 3/4 0-5 B 3/4 0-6 8 3/4 0-6 B 3/4 0-7 8 3/4 0 7 8 3/4 0-8 B 3/4 0-8 B 3/4 0-9 l
I l
l l
l
1 NPF-73 APPLICABILITY LIMITING CONDITION FOR OPERATION (Continued) 1 3.0.6 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment.
This is an exception to Limiting Condition for Operation 3.0.1 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.
SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.
4.0.2 Each Surveillanca Requirement shall be performed within the specified time interval wi*:h a maximum allowable extension not to exceed 25% of the surveillance interval.
4.0.3 Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by Specification 4.0.2, shall i
constitute noncompliance with the OPERABILITY requirements. for a Limiting Condition for Operation.
The -time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed.
The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit the
. completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Surveillance Requirements do not have to be performed on inoperable equipment.
4.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made unless the Surveillance Requirement (s) associated with a Limiting Condition for Operation has been performed within the stated surveillance interval or as otherwise specified.
This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements.
4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2 and 3 components shall be applicable as follows:
a.1 Inservice inspection of ASME Code class 1,
2 snd 3 components shall be performed in accordance with section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g).
BEAVER VALLEY - UNIT 2 3/4 0-2 Amendment No. 90
(
i NPF-73 APPLICABILITY SURVEILLANCE REQUIREMENTS a.2 Inservice testing of ASME Code Class 1, 2 and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required b'f 10 CFR 50, Section 50.55a(f).
l l
b.
Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be l
applicable.as.follows in.these Technical Specifications:,.
l l-ASME Boiler and Pressure Vessel Required frequencies for l
Code and applicable Addenda performing inservice terminology for inservice inspection and testing insoection and testina activitigg activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days c.
The provisions of Specification 4.0.2 are applicable to the above required frequencies for performing inservice inspection and testing activities.
d.
Performance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements.
l e.
Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.
I I
BEAVER VALLEY - UNIT 2 3/4 0-3 Amendment No.90 l
o NPF-73 3/4.0 APPLICABIL1?V BASES (Continued)
- trains, components and devices in the other division must be OPERABLE, or likewise satisfy Specification 3.0.5 (i.e.,
be capable of performing their design functions and have an emergency power l
source OPERABLE).
In other words, both emergency power sources must l
be OPERABLE and all redundant systems, subsystems, trains, compenente and devices in both divisions must also be OPERABLE.
If these conditions are not satisfied, action is required in accordance with this specification.
j i
In MODES 5 or 6 Specification 3.0.5 is not applicable, and thus the individual ACTION statements for each ' applicable Limiting Condition for Operation in these MODES must be adhered to.
Soecification 3.0.6 establishes the allowance for restoring equipment to service under administrative controls when it has been removed from service or declared inoperable to comply with ACTIONS.
The sole purpose of this specification is to provide an exception to Specification 3.0.1 (e.g., to not comply with the applicable ACTIONS) to allow the performance of Surveillance Requirements and post maintenance testing to demonstrate:
a.
The OPERABILITY of the equipment being returned to service; or b.
The OPERABILITY of other equipment.
i The administrative controls ensure the time the equipment is returned to service in conflict with the requirements of the ACTIONS is limited to the time absolutely necessary to perform the allowed testing.
This specification does not provide time to perform any other preventive or corrective maintenance.
Minor corrections such as adjustments of limit switches to correct position indication anomalies are considered within the scope of this specification.
Other more significant tasks such as valve packing replacement are
~
not permitted by this specification.
It is exp: ;ted that the testing will confirm equipment operability.
Should t't
- testing demonstrate that the equipment is not operable, the provisions of LCO 3.0.1 will be applied.
An example of delsonstrating the OPERABILITY of the equipment being returned to service is reopening a containment isolation valve that has been closed to comply with ACTIONS and must be reopened to perform the surveillance requirements.
l l
l l
l BEAVER VALLEY - UNIT 2 B 3/4 0-5 Amendment No. 90 l
a NPF 3/4.O APPLICABILITY l
BASES (Continued) i An example of demonstrating the OPERABILITY of other equipment is taking an inoperable channel or trip system out of the tripped condition to prevent the trip function from occurring during the performance of a surveillance requirement on another channel in the other trip system.
A similar example of demonstrating the OPERABILITY of other equipment is taking an inoperable channel or i
trip system out of the tripped condition to permit the logic to function and indicate the appropriate response during the performance of a surveillance requirement on another channel in the same trip j
l system.
Soecifications 4.0.1 throuah 4.0.5 establish the general requirements applicable to Surveillance Requirements.
These requirements are based on the Surveillance Requirements stated in the Code of Federal j
Regulations, 10 CFR 50.36 (c) (3) :
" Surveillance requirements are requirements relating to
- test, calibration, or inspection to ensure that the necessary quality of systems and components is maintained, l
that facility operation will be within safety limits, and that the limiting conditions of operation will be met."
l l
Soecifications 4.0.1 establishes the requirement that surveillances l
must be performed during the OPERATIONAL MODES or other conditions l
for which the requirements of the Limiting Conditions for Operation i
apply unless otherwise stated in an individual Surveillance Requirement.
The purpose of this specification is to ensure that l
surveillances are performed to verify the operational status of systems and components and that parameters are within specified l
limits to ensure safe operation of the facility when the plant is in l
a MODE or other specified condition for which the associated Limiting l
Conditions for Operation are applicable.
Surveillance Requirements do not have to be performed when thn facility is in an OPI: RATIONAL MODE for which the requirements of the associated Limiting Condition l
for Operation do not apply unless otherwise specified.
The Surveillance Requirements associated with a Special Test Exception I
are only applicable when the Special Test Exception is used as an allowable exception to the requirements of a specification.
Soecification 4.0.2 establishes the limit for which the specified time intervsl for Surveillance Requirements may be extended.
It permits an allowable extension of the normal surveillance interval to facilitate surveillance scheduling and consideration of plant operating conditions that may not be suitable for conducting the surveillance; e.g.,
transient conditions or other ongoing surveillance or maintenance activities.
It also provides flexibility to accommodate the length of a fuel cycle for surveillances that are performed at each refueling autage and are specified with an 18-month BEAVER VALLEY - UNIT 2 B 3/4 0-6 Amendment No.90
a NPF-73 3/4.O APPLICABILITY BASES (Continued) surveillance interval.
It is not intended that this provision be used repeatedly as a convenience to extend surveillance intervals beyond that specified for surveillances that are not performed during refueling outages.
The limitation of Specification 4.0.2 is based on engineering judgment and the recognition that the most probable result of any particular surveillance being performed is the verification of conformance with the Surveillance Requirements.
This provision is sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from the specified. surveillance interval.
Soecification 4.0.3 establishes the failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, as a condition that constitutes a failure to meet the OPERABILITY requirements for a Limiting Condition for Operation.
Under the provisions of this specification, systems and components are assumed to be OPERABLE when Surveillance Requirements have been satisfactorily performed within the specified time interval.
However, nothing in this provision is to be construed as implying that systems or components are OPERABLE when they are found or known to be inoperable although still meeting the Surveillance Requirements.
This specification also clarifies that the ACTION requirements are applicable when Surveillance Requirements have not been completed within the allowed surveillance interval and that the time limits of the ACTION requirements apply from the point in time it is identified that a surveillance has not been performed and not at the time that the allowed surveillance interval was l
exceeded.
Completion of the Surveillance Requirement within the allowable outage time limits of the ACTION requirements restores compliance with the requirements of Specification 4.0.3.
- However, i
this does not negate the fact that the failure to have performed the surveillance within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, was a violation of the OPERABILITY requirements of a Limiting Condition for Operation that is subject to enforcement action.
Further, the failure to perform a surveillance within the provisions of Specification 4.0.2 is a violation of a Technical Specification requirement and is, therefore, a reportable event under the requirements of 10 CFR 50.73 (a) (2) (i) (B) because it is a condition prohibited by the plant's Technical Specifications.
If the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or a shutdown is required to comply with ACTION requirements, e.g.,
Specification 3.0.3, a
24-hour allowance is provided to permit a delay in implementing the ACTION requirements.
This provides an adequate time limit to complete Surveillance Requirements that have not been performed.
The purpose of this allowance is to permit the completion of a surveillance before a shutdown is required to comply with ACTION requirements or before BEAVER VALLEY - UNIT 2 B 3/4 0-7 Amendment No. 90
i e NPF-73
^
3/4.0 APPLICABILITY BASES (Continued) other remedial measures would be required that may preclude completion of a surveillance.
The basis for this allowance includes consideration for plant conditions, adequate planning, availability of personnel, the time required to perform the surveillance, and the safety significance of the delay in completing the required surveillance.
This provision also provides a time limit for the completion of Surveillance Requirements that become applicable as a consequence of MODE changes imposed by ACTION requirements and for completing Surveillance Requirements that are applicable when an exception to the requirements of_ Specification 4.0.4 is allowed.
If a surveillance is not completed within the 24-hour allowance, the time limits of the ACTION requirements are applicable at that time.
When a surveillance is performed within the 24-hour allowance and the Surveillance Requirements are not met, the time limits of the ACTION requirements are applicable at the time that the surveillance is terminated.
Surveillance Requirements do not have to be performed on inoperable equipment because the ACTION requirements define the remedial measures that apply.
However, the Surveillance Requirements have to be met t o demonstrate that inoperable equipment has been restored to OPERABLL status.
Soecification 4.0.4 establishes the requirement that all applicable surveillances must be met before entry into an OPERATIONAL MODE or other condition of operation specified in the Applicability statement.
The purpose of this specification is to ensure that system and component OPERABILITY requirements or parameter limits are met before entry into a MODE or condition for which these systems and components ensure safe operation of the facility.
This provision applies to changes in OPERATIONAL MODES or other specified conditions associated with plant shutdown as well as startup.
Under the provisions of this specification, the applicable Surveillance Requirements m"st be performed within the specified surveillance interval to ensure that the Limiting Conditions for Operation are met during initial plant startup or following a plant outage.
When a shutdown is required to comply with ACTION requirements, the provisions of Specification 4.0.4 do not apply because this would delay placing the facility in a lower MODE of operation.
BEAVER VALLEY - UNIT 2 B 3/4 0-8 Amendment No.90
5 u
NPF-73 3/4.0 APPLICABILITY BASES (Continued) t snecification 4.0.5 establishes the requirement that inservice inspection of ASME Code Class 1,
2, and 3 components and inservice testing of ASME Code Class 1,
2, and 3 pumps and valves shall be performed in accordance with a periodically updated version of Section XI of the ASME Boiler and pressure Vessel Code and Addenda as required by 10 CFR 50.55a.
These requirements apply except when relief has been provided in writing by the commission.
This specification includes a clarification of the frequencies for performing the inservice. inspection and testing activities required by Section XI of the ASME Boiler and Pressure Vessel Code and I
applicable Addenda.
This clarification is provided to ensure consistency in surveillance intervals throughout the Technical specifications and to remove any ambiguities relative to the frequencies for performing the required inservice inspection and testing activities.
Under the terms of this specification, the more restrictive requirements of the Technical Specifications take precedence over the ASME Boiler and Pressure Vessel Code and applicable Addenda.
The requirements.
of Specification 4.0.4 to perform surveillance activities before entry into an OPERATIONAL MODE or other specified condition takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows pumps and valves to be tested up to one week after return to normal operation.
The Technical Specification definition of OPERABLE does not allow a grace period before a component that is not capable of performing its specified function, is declared inoperable and takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows a valve to be incapable of performing its specified function for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before being declared inoperable.
BEAVER VALLEY - UNIT 2 B 3/4 0-9 Amendment No.90