ML20012E966
| ML20012E966 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 03/22/1990 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Duquesne Light Co, Ohio Edison Co, Pennsylvania Power Co |
| Shared Package | |
| ML20012E967 | List: |
| References | |
| DPR-66-A-152, NPF-73-A-029 NUDOCS 9004090179 | |
| Download: ML20012E966 (11) | |
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NUCLEAR REGULATORY COMMISSION W
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t DUQUE5NE L14NT COMPANY OH10 ED1$0N COMPANY PENN5YLVANIA POWER COMPANY t
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DOCKET NO. 60-3H l
BEAVER VALLEY POWER STATION. UNIT NO. 1 l
AMENDMENT TO FACILITY OPERATING LICENSE I
Amendment No. 152 l
License No. DPR 66 l
1.
The Nuclear Regulatory Comission (the Comission) has found that A.
The application for amendment by Duquesne Light Company, et al.
l (thelicensee)datedDecember 12,1989 comp 1 es with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter 1 B.
The facility will operate in conformity'with the application, the provisions of the Act, and the rules and regulations of i
the Comission; C.
Thereisreasonableassurance(1)thattheactivitiesauthorized i
by thit amendment can be condu ted without endantiering the health and safety of the public, and (ii) that such act'vities will be t
conducted in compliance with the Comission's regulations; I
D.
The issuance of this amendment will not be inimical to the common l
defense and security or to the health and safety of the public; l
and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission'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 y
amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-66 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised throuch Amendment No.152, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective on issuance.
FOR THE NUCLEAR R ORY COMMi$$10N O
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. Stolz, irector /
Project Directorate 1-4 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications t
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Date of issuance: March 22,1990 W
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n ATTACHMENT TO LICENSE AMENDMENT NO.152 1
FACILITY OPERATING LICENSE N0. DPR-66 DOCKET NO. 50 334
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Replace the following pages of the Appendix A (Technical Specifications)by with the enclosed pages as indicated.
The revised pages are identified amendment nurber and contain vertical lines indicating the areas of change.
i Remova Insert 3/4 0-2 3/4 0-2 l
83/4 0-5 83/4 0-5 i
B3/4 0-6 B3/4 0-6 f
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3/4.0 APPLICABILITY SURVEILLANCE REQUIREMENTS 1.
At least NOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, i
2.
At least HOT SNUTDOWN 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 SKUTDOWN 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.
4.0.1 Surveillance Requirements shall be met during the OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for Operation unless otherwise wtated in an individual Surveillance Requirement.
4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with a
maximum allowable extension not to exceed 25% of the surveillance interval.
4.0.3 Failure to perform a
surveillance Requirement within the I
allowed surveillance interval, defined by Specification 4.0.2, shall 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 l
of ASME Code class 1,
2 and 3 components shall be applicable as follows:
a.
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 Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CTR 50, Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g) (6) (1).
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 applicable as follows in these Technical Specifications:
BEAVER VALLEY - UNIT 1 3/4 0-2 Miendment No.14,7$4,152 I
l 3/4.0 APPLICABILITY J
BASES (Con't)
- 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 source OPERABL2).
In other words, both emergency power sources must be OPERABLZ and all redundant systems, subsystems, trains, components and devices in both divisions must also be OPERABLE.
If these conditions are not satisfied, action is required in accordance with this specification.
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 tot.
Soecification 4.0.1 throuah 4.0.5 establish the general requirements applicable to curveillance Requirements.
These requirements are based on the Surveillance Requirements stated in the code of Federal Regulations, 10 CTR 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 l
will be within safety limits, and that the limiting conditions of operation will be met".
l Specification 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 MODE or other specified condition for which the associated Limiting a
conditions for operation are applicable.
Surveillance Requirements 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 Su rveillance Requirements associated with a Special Tes'; Exception are only applicable when the Special Test Exception is used as an allowable exception to the requirements of a Specification.
Specification 4.0.2 establishes the limit for which the specified time interval Tor 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 acconnodate the length of a fuel cycle for surveillances that are performed at each refueling outage and are specified with an 18-month 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 judgement and the recognition that the most probable BEAVER VALLEY - UNIT 1 B 3/4 0-5 AmendmentLA$@iS @R
3/4.0 APPLICABILITY BASES (Con't) result of any particular surveillance being performed is the verification of conformance with the surveillance Re pirements.
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.
Specification 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 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 3
r implying that systems or components are OPERABLE when they are found t
L 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 i
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 sutveillance within the provisions of Specification 4.0.2 is a violation of a o
l Technical Specification requirement and is, therefore, a reportable 0
event under the requirements of 10 CFR 50.73 (a) (2) (1) (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 other remedial measures would be required that may preclude l
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 Surveillancu 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 BEAVER VALLEY - UNIT 1 B 3/4 0-6 Amendment No. Te9JM
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NUCLEAR REGULATORY COMMIS$10N
- .t WASMHv0 TON, D. C. 30006 j
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l RDUESNE LIGHT COMPANY OH10 ED!$0N COMPANY l
THE CLEVELAND [LECTRIC ILLUNINATING COMPANY
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THE TOLEDO E01$0N COMPANY I
i DOCKET N0. 50-412
'l BEAVER VALLEY POWER STATION. UNIT NO. t AMENDMENT'T0 FACILITY 0PERATING LICENSE Amendment No. 29 License No. NPF-73 1.
The Nuclear Regulatory Comission (the Comission) has found that:
i A.
The application for amendment by Duquesne Light Company, et.a1.
(the-licensee)datedDecember 12, 1989 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the t
' Act) and the Comission's rules and reg,ulations set forth in 10 CFR Chapter I; i
B.
The facility will oserate in conformity with the application, the provisions of the Act, and the rules and regulations of
- the Comission; C.
Thereisreasonableassurance(1)thattheactivitiesauthorized 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 Comission'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
' t.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment,andparagraph2.C.(2)ofFacilityOperatingLicense No. NPF-73 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 29, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in the license. DLC0 shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective on issuance.
I FOR THE NUCLEAR REcittl, TORY COMMISSION s
Ig.n Jo n F. Stolz, Directo Project Directorate 1 4 Division of Reactor Projects. 1/I1 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: March 22, 1990 4
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ATTACHMENT TO LICENSE AMENDMENT NO. 29 t
FACILITY OPERATING LICENSE N0. NPF-73 DOCKET NO. 50-412 Replace the'following pages of the Appendix A (Technical Specifications) with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert 3/4 0-2 3/4 0-2 B3/4 0-5 B3/4 0-5
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1 APPLICABILITY
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SURVEILLANCE REQUIREMENTS i
4.0.1 Surveillance Requirements shall be met during the OPERATIONAL MDDES or 1
other conditions specified for individual Limiting Conditions for Operation i
unless otherwise stated in an individual Surveillance Requirement.
l 4.0.2' Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the
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surveillance interval.
4.0.3 Failure to perform a Surveillance Requirement within the allowed surveil-lance interval, defined by Specification 4.0.2, shall constitute noncompliance with the OPERABILITY requirements for a Limitinn Condition for Operation. The time limits of the ACTION requirements are app 1' cable at the time it is identi-1 fled that a Surveillance Requirement has not been performed. The ACTION i
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 i
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:
Inservice inspection of ASME Code Class 1, 2 and 3 components and a.
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 by
[
10 CFR 50, Section 50.55a(g), except where specific written relief I
has been granted by the Commission pursuant to 10 CFR 50, Sec-tion 50.55a(g)(6)(1).
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 applicable as follows in these Technical Specifications:
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BEAVER VALLEY - UNIT 2 3/4,0-2 Amendment No. M 29
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i 3/4.0 APPLICABILITY BASES (Continued)
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i trains, components and devices in the other division must be OPERABLE, or like-l wise 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, trains, components and devices in both divisions must also be OPERABLE.
If i
these conditions are not satisfied, action is required in accordance with this specification.
i l
In MODES 5 or 6 Specification 3.0.5 is not applicable and thus the indi-vidualACTIONstatementsforeachapplicableLimitingCondItionforOperation in these MODES must be adhered to.
i Specifications 4.0.1 throu1h 4.0.5 establish the general requirements applicable to Surveillance Requiremen;s.
These requirements are based on the Surveillance i
Requirements stated in the Code of Federal Regulations, 10 CFR 50.36(c)(3)-
l
" Surveillance requirements are requirements relating to test, calibration, or inspection to ensure that the necessary quality of systems and components is i
maintained, that facility operation will be within safety limits, and that the limiting conditions of operation will be met."
Specifications 4.0.1 establishes the requirement that surveillances must be i
performed during the OPERATIONAL MODES or other conditions for which the t
requirements of the Limiting Conditions for Operation apply unless otherwise stated in an individual Surveillance Requirement.
The purpose of this specifi-cation 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
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other specified condition for which the associated Limiting Conditions for Operation are applicable.
Surveillance Requirements do not have to be performed i
when the facility is in an OPERATIONAL MODE for which the requirements of the associated Limiting Condition for Operation do not apply unless otherwise I
specified.
The Surveillance Requirements associated with a Special Test Excep-i tion are only applicable when the Special Test Exception is used as an allow-l able exception to the requirements of a specification.
Specification 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 surveil-lance scheduling and consideration of plant operating conditions that may not i
be suitable for conducting the surveillance; e.g., transient conditions or i
other ongoing surveillance or maintenance activities.
It also provides flex-l ibility to accommodate the length of a fuel cycle for surveillances that are I
performed at each refueling outage and are specified with an 18-month 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 l
BEAVER VALLEY - UNIT 2 B 3/4 0-5 Amendment No. 4, 29 I
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