ML071240263
| ML071240263 | |
| Person / Time | |
|---|---|
| Site: | Surry  (DPR-032, DPR-037) |
| Issue date: | 05/03/2007 |
| From: | NRC/NRR/ADRO/DORL/LPLII-1 |
| To: | |
| Lingam, Siva NRR/DORL 415-1564 | |
| Shared Package | |
| ML070930172 | List: |
| References | |
| TAC MD4206, TAC MD4207, TSTF-358 | |
| Download: ML071240263 (7) | |
Text
.3-
- 3.
This renewed license shall be deemed to contain and Is subject to the condlions specified In the following Commission regulations: 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Sections 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 GFR Part 70; and is subject to ali.appficable provisions of the Act and the..
rules, regulations, and orders of the Commission now or hereafter-in effect; and is subject to the additional conditions specified below:
A.
Maximum Power Level The licensee Is authorized to operate the facility at steady state reactor core power levels not In excess of 2546 nMegawatts (thermal).
B.
Technical Soeciffcatlons The Technical Specifications.contalhed In Appendix A, as revised through Amendment No. 253are hereby Incorporated In the renewed license.
The licensee shall operate the facility In accordance with the Technical Speclicalons.
C.
Reports The licensee shall make certain reports In accordance with the requirements of the Technical Specifications.
D.
Records The licensee shall keep facility operating records In accordance with the requirements of the Technical Specifications.
E.
Deleted by Amendment 65 F.
Deleted by Amendment 71 G.
Deleted by Amendment 227 HI.
Deleted by Amendment 227 I.
Fire Prolection The licensee shall Implemeht and maintain In effect the provisions of the approved fire protection program as described In the Updated Final Safety Analysis Report and as approved In the SER dated September 19, 1979, (and Supplements dated May 29, 1980, October 9, 1980, December 18, 1980, February 13, 1981, December 4, 1981, April 27, 1982, November 18, 1982, January 17, 1984, February 25, 1988, and Renewed Ucense No. DFR-32 Amendment No. 253 E.
Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproddct and special nuclear materials as may be produced by the operation of the facility.
.3.-
This renewed license shall be deemed to contain and Is subject to. the conditions.
specified in the following Commission regulations: 10 CFR Part 20, Section 30.34 of 10 OFR Part 30, Section 40.41 of IOCFR Part 40, Sections 50.54 and 60.69 of 10 CFR Part 50, and Section 70.32 of 10 CF' Part 70; and Is subject to all applicable provisions of the Act and the rules, regulations, and orders of the Commission now or hereafter In effect; and is subject to the additional conditions specified below:.
A.
Maximum Power Level The licensee Is authorized to operate the facility at steady stale reactor core power levels not In excess of 2548 megawatts (thermal).
B.
Technical Soeclilcations The Tehnilcal Speclficstions contained In AppendIxA, as revised through Amendment No. 252'Ve hereby Incorporated In this renewed license.
The licensee shai, opeiate the facility In accordance with the Technical Specifications.
C.
Repoors The licensee shall make certaln reports In accordance with the requirements of the Technical Soiecifications.
D.
Records The licensee shagl keep facility operating records In accordance with the
.requirements of the Technical Specifications.
E.
Deleted by Amnendment 54 F.
Deleted by Amendment 59 and Amendment 65 G.
Deleted by Amendment 227 H-.
Deleted by Amendment 227.
Renewed License N6. DPR-37 Amendment No. 252
TS 4.0-1 4.0 SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements (SRs) shall be met during the REACTOR OPERATION conditions or other specified conditions in the individual Limiting Conditions for Operation (LCO), unless otherwise stated in the SR. Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the LCO. Failure to perform a Surveillance within the specified frequency shall be failure to meet the LCO except as provided in SR 4.0.3. Surveillances do not have to be performed on inoperable equipment or variables outside specified limits.
4.0.2 Surveillance requirement specified time intervals may be adjusted plus or minus 25 percent to accommodate normal test schedules.
4.0.3 If it is discovered that a Surveillance was not performed within its specified frequency, then compliance with the requirement to declare the LCO not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified frequency, whichever is greater. This delay period is permitted to allow performance of the Surveillance. A risk evaluation shall be -performed for any Surveillance delayed greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and the risk impact shall be managed.
If the Surveillance is not performed within the delay period, the LCO must immediately be declared not met, and the applicable action(s) must be taken.
When the Surveillance is performed within the delay period and the Surveillance is not met, the LCO must immediately be declared not met, and the applicable action(s) must be taken.
4.0.4 Entry into an operational condition shall not be made unless the surveillance requirement(s) associated with a Limiting Condition of Operation has been performed within the stated surveillance interval or as otherwise specified. This provision shall not prevent passage through or to operational conditions as required to comply with Action Statement requirements.
AmendmentNos. 253, 252
TS 4.0-2 BASES 4.0.1 Surveillance Requirement (SR) 4.0.1 establishes the requirement that SRs must be met during the REACTOR OPERATION conditions or other specified conditions in the individual Limiting Conditions for Operation (LCO) that apply, unless otherwise specified in the individual SRs. This Specification is to ensure that Surveillances are performed to verify the operability of systems and components, and that variables are within specified limits. Failure to meet a Surveillance within the specified frequency, in accordance with SR 4.0.2, constitutes a failure to meet an LCO. Surveillances may be performed by means of any series of sequential, overlapping, or total steps provided the entire Surveillance is performed within the specified frequency.
Systems and components are assumed to be OPERABLE when the associated SRs have been met. Nothing in this Specification, however, is to be construed as implying that systems or components are OPERABLE when:
- a.
The systems or components are known to be inoperable, although still meeting the SRs; or
- b.
The requirements of the Surveillance(s) are. known not to be met between re-quired Surveillance performances.
Surveillances do not have to be performed when the unit is in a REACTOR OPERATION condition or other specified condition for which the requirements of the associated LCO are not applicable, unless otherwise specified. The SRs associated with a test exception are only applicable when the test exception is used as an allowable exception to the requirements of a Specification.
Unplanned events may satisfy the requirements (including applicable acceptance criteria) for a given SR. In this case, the unplanned event may be credited as fulfilling the performance of the SR. This allowance includes those SRs whose performance is normally precluded in a given REACTOR OPERATION condition or other specified condition.
Surveillances, including Surveillances invoked by Action Statements, do not have to be performed on inoperable equipment because the Action Statements define the remedial measures that apply. Surveillances have to be met and performed in accordance with SR 4.0.2, prior to returning equipment to OPERABLE status.
Amendment Nos. 253, 252
TS 4.0-3 Upon completion of maintenance, appropriate post maintenance testing is required to declare equipment OPERABLE. This includes ensuring applicable Surveillances are not failed and their most recent performance is in accordance with SR 4.0.2. Post maintenance testing may not be possible in the current REACTOR OPERATION condition or other specified conditions in the individual LCO due to the necessary unit parameters not having been established. In these situations, the equipment may be considered OPERABLE provided testing has been satisfactorily completed to the extent possible and the equipment is not otherwise believed to be incapable of performing its function. This will allow operation to proceed to a REACTOR OPERATION condition or other specified condition where other necessary post maintenance tests can be completed.
An example of this process is Auxiliary Feedwater (AFW) pump turbine maintenance during refueling that requires testing at steam pressures that cannot be obtained until the unit is at HOT SHUTDOWN conditions. However, if other appropriate testing is satisfactorily completed, the AFW System can be considered OPERABLE. This allows startup and other necessary testing to proceed until the plant reaches the steam pressure required to perform the testing.
4.0.2 The provisions of this specification provide allowable tolerances for performing surveillance activities beyond those specified in the nominal surveillance interval.
These tolerances are necessary to provide operational flexibility because of scheduling and performance considerations. The phrase "at least" associated with a surveillance frequency does not negate this allowable tolerance value and permits the performance of more frequent surveillance activities.
4.0.3 SR 4.0.3 establishes the flexibility to defer declaring affected equipment inoperable or an affected variable outside the specified limits when a Surveillance has not been completed within the specified frequency. A delay period of up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified frequency, whichever is greater, applies from the point in time that it is discovered that the Surveillance has not been performed in accordance with SR 4.0.2, and not at the time that the specified Surveillance frequency was not met.
This delay period provides adequate time to complete Surveillances that have been missed. This delay period permits the completion of a Surveillance before
.complying with the Action Statement(s) or other remedial measures that might preclude completion of the Surveillance.
AmendmentNos. 253, 252
TS 4.0-4 The basis for this delay period includes consideration of unit conditions, adequate planning, availability of personnel, the time required to perform the Surveillance, the safety significance of the delay in completing the required Surveillance, and the recognition that the most probable result of any particular Surveillance being performed is the verification of conformance with the requirements.
When a Surveillance with a frequency based not on time intervals, but upon specified unit conditions, operating situations, or requirements of regulations (e.g.,
prior to entering POWER OPERATION after each fuel loading, or in accordance with 10 CFR 50, Appendix J, as modified by approved exemptions, etc.) is discovered to not have been performed when specified, SR 4.0.3 allows for the full delay period of up to the specified frequency to perform the Surveillance.
However, since there is not a time interval specified, the missed Surveillance should be performed at the first reasonable opportunity.
SR 4.0.3 provides a time limit for, and allowances for the performance of, Surveillances that become applicable as a consequence of REACTOR OPERATION condition changes imposed by Action Statements.
Failure to comply with the specified frequencies for SRs is expected to be an infrequent occurrence. Use of the delay period established by SR 4.0.3 is a flexibility which is not intended to be used as an operational convenience to extend Surveillance intervals. While up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or the limit of the specified frequency is provided to perform the missed Surveillance, it is expected that the missed Surveillance will be performed at the first reasonable opportunity. The determination of the first reasonable opportunity should include consideration of the impact on plant risk (from delaying the Surveillance as well as any plant configuration changes required or shutting the plant down to perform the Surveillance) and impact on any analysis assumptions, in addition to unit conditions, planning, availability of personnel, and the time required to perform the Surveillance. This risk impact should be managed through the program in place to implement 10 CFR 50.65(a)(4) and its implementation guidance, NRC Regulatory Guide 1. 182, "Assessing and Managing Risk Before Maintenance Activities at Nuclear Power Plants." This Regulatory Guide addresses consideration of temporary and aggregate risk impacts, determination of risk management action thresholds, and risk management action up to and including plant shutdown. The missed Surveillance should be treated as an emergent condition as discussed in the Regulatory Guide. The risk evaluation may use Amendment Nos.
253, 252
TS 4.0-5 quantitative, qualitative, or blended methods. The degree of depth and rigor of the evaluation should be commensurate with the importance of the component. Missed Surveillances for important components should be analyzed quantitatively. If the results of the risk evaluation determine the risk increase is significant, this evaluation should be used to determine the safest course of action. All missed Surveillances will be placed in the licensee's Corrective Action Program.
If a Surveillance is not completed withinthe allowed delay period, then the equipment is considered inoperable or the variable is considered outside the specified limits and the Allowed Outage Time(s) of the Action Statement(s) for the applicable LCO conditions begin immediately upon expiration of the delay period.
If a Surveillance is failed within the delay period, then the equipment is inoperable, or the variable is outside the specified limits and the Allowed Outage Time(s) of the Action Statement(s) for the applicable LCO conditions begin immediately upon the failure of the Surveillance.
Completion of the Surveillance within the delay period allowed by this Specification, or within the Allowed Outage Time(s), of the Action Statement(s),
restores compliance with SR 4.0.1.
4.0.4 This specification establishes the requirement that all applicable surveillances must be met before entry into an operational condition 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 condition for which these systems and components ensure safe operation of the facility. This provision applies to changes in operational 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.
Exceptions to Specification 4.0.4 allow performance of surveillance requirements associated with a Limiting Condition for Operation after entry into the applicable operational condition.
When a shutdown is required to comply with Action Statement requirements, the provisions of Specification 4.0.4 do not apply because this would delay placing the facility in a lower condition of operation.
Amendment Nos.
253, 252