ML20236K633
| ML20236K633 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 07/02/1998 |
| From: | Chandu Patel NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20236K636 | List: |
| References | |
| NUDOCS 9807100018 | |
| Download: ML20236K633 (8) | |
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UNITED STATES g
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 3066H001 o
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1 ENTERGY OPERATICNS. INC.
DOCKET NO. 50-332 l
WATERFORD STEAM ELECTRIC STATION. UNIT 3 i
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.143 Ucense No. NPF-38 1
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated June 3,1997, as supplemented by letter dated May 1,1998, 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.
9807100018 990702 PDR ADOCK 05000382 p
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2-2.
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-38 is hereby amended to read as fo!!ows:
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 143, and the Environmental Protection Plan contained in Appandix B, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance, to be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 1
&h Chandu P. Patel, Project Manager Project Directorate IV-1 l
l Division of Reactor Projects lil/lV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 2, 1998 l
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ATTACHMENT TO LICENSE AMENDMENT NO.143 TO FACILITY OPERATING LICENSE NO. NPF-38 QQCKET NO. 50-382 Replace the following pages of the Appendix A Technical Specifications with the attached pages.
i The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change. The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE PAGES INSERT PAGES 3/4 3-15 3/4 3-15 3/4 3-18a 3/4 3-18a B 3/4 3-1 B 3/4 3-1 l
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O TABLE 3.3-3 (Continued)
TABLE NOTATION ACTION 18 -
With more than one channel inoperable, or if the inoperable channel cannot be placed in the trip (D.C. Relay energized) condition, declare the associated Emergency Diesel Generator inoperable and take the ACTION required by Specification 3.8.1.1. The surveillance requirements of Table 4.J-2 are waived for all channels while this action requirement is in effect.
ACTION 19 -
With the number of channels OPERABLE one less than the Total Number of Channels, STARTUP and/or POWER OPERATION and/or operation in the other applicable MODE (S) may continue, provided the inoperable channel is placed in the bypassed or tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; a.
If the inoperable channel is to remain in the bypassed condition, the desirability of maintaining this channelin the bypassed condition shall be documented by the Plant Operations Review Committee in accordance with plant administrative procedures. The channel shall be retumed to OPERABLE status no later than prior to entry into the applicable MODE (S) following the next COLD SHUTDOWN.
b.
If the inoperable channelis required to be placed in the tripped condition, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> either restore the channel to OPERABLE status or place the channelin the bypassed condition. If the tripped channel can not be returned to OPERABLE status in 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, be in 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 /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> or place the tripped channelin bypass.
ACTION 20 -
With the number of OPERABLE channels one less than the Minimum Channels OPERABLE, STARTUP and/or POWER OPERATION and/or operation in the other applicable MODE (S) may continue provided the following conditions are satisfied:
a.
Verify that one of the inoperable channels has been bypassed and place the other inoperable channelin the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
b.
Restore at least one of the inoperable channels to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in 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 /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. Subsequent operation in the applicable MODE (S) may continue if one channel is restored to OPERABLE status and the provisions of ACTION 19 are satisfied.
WATEnt ORD - UNIT 3 3/4 3-18a Amendment No. 47,143
3/4 3 INSTRUMENTATION BASER 3/4 31 and 3/4 3.2 REACTOR PROTECTIVE AND ENGINEFRFn SAFETY FEATURER ACTUATION SYSTEMS INSTRUMENTATION The OPERABILITY of the Reactor Protective and Engineered Safety Features Actuation Systerm instrumentation and bypasses ensures that (1) the associated Engineered Safety Features Actuation action and/or reactor trip will be initiated when the parameter monitored by each channel or combination thereof reaches its setpoint, (2) the specified coincidence logic is maintained, (3) sufficient redundancy is maintained to permit a channel to be out of service for testing or maintenance, and (4) sufficient system functional capability is available from diverse parameters.
The OPERABILITY of these systems is required to provide the overall reliability, redundancy, and diversity assumed available in the facility design for the protection and mitigation of accident and transient conditions. The integrated operation of each of these systems is consistent with the assumptions used in the safety analyses.
4 The redundancy design of the Control Element Assembly Calculators (CEAC) provides i
reactor protection in the event one or both CEACs become inoperable, if one CEAC is in test or inoperable, verification of CEA position is performed at least every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. If the second CEAC fails, the CPCs will use DNBR and LPD penalty factors to restrict reactor operation to some maximum fraction of RATED THERMAL POWER. If this maximum fraction is exceeded, a reactor trip will occur.
Table 3.3-3 ACTION 19 allows for continued operation in the applicable MODE (S) with
)
one of the Refueling Water Storage Pool (RWSP)- Low channels inoperable provided the channel is placed in the bypass or tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, if an inoperable channel of l
the RWSP - Low is required to be placed in the tripped condition within one hour, then within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> the channel must either be restored to OPERABLE status or be placed in the bypassed condition. The bypassed chanre' must be restored to OPERABLE status prior to entering MODE 4 following the next MO4 5 entry. With one of the RWSP - Low channels inoperable and in bypass, and testing or repairs is necessary on one of the remaining channels, ACTION 20 must be entered.
ACTION 19a is annotated with an askerisk for the 3.0.4 exemption to allow the changing of MODES even though one channelis bypassed. MODE changes between MODES 1 and 4 with this configuration are allowed, to permit maintenance and testing on the inoperable channel, in this configuration, the protection system is in a two-out-of-three logic, and the probability of a random failure affecting two of the OPERABLE channels is remote. The tripped condition does not have this annotation as a single failure could cause the Emergency Core Cooling System and Containment Spray System suctions to be supplied from the Safety injection System Sump prematurely and loss of the Low Pressure Safety injection Systems.
Table 3.3-3 ACTION 20 allows for continued operation in the applicable MODE (S) with two of the RWSP - Low channels inoperable provided that one of the inoperable channels is bypassed and the other inoperable channel is placed in the tripped condition within one hour.
One of the inoperable RWSP - Low channels must be restored to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> to allow removal of the channel from the tripped condition. The allowed time is acceptable because operating experience has demonstrated the low probability of the following sequence of events occuring: the need to place one RSWP - Low channe! in the tripped WATERFORD - UNIT 3 B 3/4 3-1 Amendment No. 69,ft3,143
3/4 3 INSTRUMENTATION BASES 3/4 3.1 and 3/4 3 2 REACTOR PROTECTIVE AND ENGINFFRFD SAFETY FEATURES ACTUATION SYSTEMS INSTRUMENTATION condition while another RWSP - Low channel is in bypass, the receipt of a valid Safety injection Actuation Signal Actuation, and a coincident failure of one of the two remaining OPERABLE RWSP - Low channels. These conditions could cause the Emergency Core Cooling System and Containment Spray System suctions to be supplied from the Safety injection System Sump prematurely due to containment pressure being higher than RWSP outiet pressure and loss of the Low Pressure Safety injection Systems.
j When one of the inoperable channels is restored to OPERABLE status, subsequent operation in the applicable MODE (S) may continue in accordance with the provisions of ACTION 19.
4 The Surveillance Requirements specified for these systems ensure that the overall system functional capability is maintained comparable to the original design standards. The periodic surveillance tests performed at the minimum frequencies are sufficient to demonstrate this capability. The quarterly frequency for the channel functional tests for these systems comes from the analyses presented in topical report CEN-327: RPSESFAS Extended Test interval Evaluation, as supplemented.
RPS\\ESFAS Trip Setpoints values are determined by means of an explicit setpoint calculation analysis. A Total Loop Uncertainty (TLU) is calculated for each RPSESFAS instrument channel. The Trip Setpoint is then determined by adding or subtracting the TLU from the Analytical Limit (add TLU for decreasing process value; subtract TLU for increasing process value). The Allowable Value is determined by adding an allowance between the Trip Setpoint and the Analytical Limit to account for RPSESFAS cabinet Periodic Test Errors (PTE) which are present during a CHANNEL FUNCTIONAL TEST. PTE combines the RPSESFAS cabinet reference accuracy, calibration equipment errors (M&TE), and RPSESFAS cabinet b! stable Drift. Periodic testing assures that actual setpoints are within their Allowable Values. A channel is inoperable if its actual setpoint is not within its Allowable Value and corrective action must be taken. Operation with a trip set less conservative than its setpoint, but within its specified ALLOWABLE VALUE is acceptable on the basis that the difference between each trip Setpoint and the ALLOWABLE VALUE is equal to or less than the Periodic Test Error allowance assumed for each trip in the safety analyses.
The measurement of response time at the specified frequencies provides assurance that the protective and ESF action function associated with each channel is completed within the time limit assumed in the safety analyses. No credit was taken in the analyses for those channels with response times indicated as not applicable.
Response tirne may be demonstrated by eny series of sequential, overlapping, or total channel test measurements provided that such tests demonstrate the total channel response time as defined. Sensor response time verification may be demonstrated by either (l) in place, onsite, or offsite test measurements cr (2) utilizing replacement sensors with certified response times.
WATERFORD - UNIT 3 B 3/4 3-ia Amendment No. 4+3,143
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