ML031610992
| ML031610992 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 06/05/2003 |
| From: | Bauer S Arizona Public Service Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 102-04952-SAB/TNW/DWG | |
| Download: ML031610992 (17) | |
Text
Scott A. Bauer Department Leader Regulatory Affairs Palo Verde Nuclear Generating Station Technical Specification 5.5.14 Tel: 6231393-5978 Mail Station 7636 Fax: 623/393-5442 P.O. Box 52034 e-mail: sbauer@apsc.com Phoenix, AZ 85072-2034 1 02-04952-SAB/TNW/DWG June 5, 2003 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-37 Washington, DC 20555-0001
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2, and 3 Docket Nos. STN 50-52815291530 Technical Specifications Bases Revision 22 Update Pursuant to PVNGS Technical Specification (TS) 5.5.14, "Technical Specifications Bases Control Program," Arizona Public Service Company (APS) is submitting changes to the TS Bases incorporated into Revision 22, implemented on June 5, 2003. The Revision 22 insertion instructions and replacement pages are provided in the Enclosure.
No commitments are being made to the NRC by this letter.
Should you have any questions, please contact Thomas N. Weber at (623) 393-5764.
Sincerely, SAB/TNW/DWG/kg
Enclosure:
PVNGS Technical Specification Bases Revision 22 Insertion Instructions and Replacement Pages cc:
Regional Administrator, NRC Region IV J. N. Donohew N. L. Salgado A member of the STARS (Strategic Teaming and Resource Sharing) Alliance callaway
- Comanche Peak
- Diablo Canyon
- Palo verde
- South Texas Project
- wolf creek wAPS Po l
ENCLOSURE PVNGS Technical Specification Bases Revision 22 Insertion Instructions and Replacement Pages
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RCS Operational LEAKAGE RCS Operational LEAKAGE B 3.4.14 BASES LCO RCS operational LEAKAGE shall be limited to:
- a.
Pressure Boundary LEAKAGE No pressure boundary LEAKAGE is allowed, being indicative of material deterioration. LEAKAGE of this type is unacceptable as the leak itself could cause further deterioration, resulting in higher LEAKAGE.
Violation of this LCO could result in continued degradation of the RCPB. LEAKAGE past seals and gaskets is not pressure boundary LEAKAGE.
- b.
Unidentified LEAKAGE One gallon per minute (gpm) of unidentified LEAKAGE is allowed as a reasonable minimum detectable amount that the containment air monitoring and containment sump level monitoring equipment can detect within a reasonable time period. Violation of this LCO could result in continued degradation of the RCPB. if the LEAKAGE is from the pressure boundary.
- c.
Identified LEAKAGE Up to 10 gpm of identified LEAKAGE is considered alowable because LEAKAGE is from known sources that do not interfere with detection of unidentified LEAKAGE and is well within the capability of the RCS makeup system.
Identified LEAKAGE includes LEAKAGE to the containment from specifically known and located sources, but does not include pressure boundary LEAKAGE or controlled Reactor Coolant Pump (RCP) seal leakoff (a normal function not considered LEAKAGE).
Violation of this LCO could result in continued degradation of a component or system.
(continued)
PALO VERDE UNITS 1.2,3 B 3.4.14-3 REVISION 22
RCS Operational LEAKAGE B 3.4.14 BASES I
LCO (continued)
LCO 3.4.15. "RCS Pressure Isolation Valve (PIV)
Leakage." measures leakage through each individual PIV and can impact this LCO. Of the two PIVs in series in each isolated line, leakage measured through one PIV does not result in RCS LEAKAGE when the other is leaktight.
If both valves leak and result in a loss of mass from the RCS. the loss must be included in the allowable identified LEAKAGE.
- d.
Primary to Secondary LEAKAGE through Any One SG The maximum allowable operational primary to secondary LEAKAGE through any one SG of 150 gpd is based on operating experience as an indication of one or more propagating tube leak mechanisms. This operational limit is significantly less than the initial conditions assumed in the safety analyses.
The Steam Generator Tube Surveillance Program described in TS Section 5.5.9 ensures that the structural integrity of the SG tubes is maintained.
The 150 gpd leakage rate limit provides additional assurance against tube rupture at normal and faulted conditions and provides additional assurance that cracks will not propagate to burst prior to detection by leakage monitoring methods and commencement of plant shutdown.
Primary to secondary LEAKAGE must be included in the total allowable limit for identified LEAKAGE.
APPLICABILITY In MODES 1, 2. 3. and 4. the potential for RCPB LEAKAGE is greatest when the RCS is pressurized.
In MODES 5 and 6. LEAKAGE limits are not required because the reactor coolant pressure is far lower, resulting in lower stresses and reduced potentials for LEAKAGE.
(continued)
PALO VERDE UNITS 1,2,3 B 3.4.14-4 REVISION 7
SITs -
Shutdown B 3.5.2 BASES ACTIONS A.1 (Continued)
If one of the required SITs is inoperable due to the inability to verify level or pressure, the SIT must be returned to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Section 7.4 of NUREG-1366 (Ref. 4) discusses surveillance requirements in technical specifications for the instrument channels used in the measurement of water level and pressure in SITs.
The following statement is made in Section 7.4 of NUREG-1366 (Ref. 4):
"The combination of redundant level and pressure instrumentation [for any single SIT] may provide sufficient information so that it may not be worthwhile to always attempt to correct drift associated with one instrument [with resulting radiation exposures during entry into containment] if there were sufficient time to repair one in the event that a second one became inoperable.
Because these instruments do not initiate a safety action, it is reasonable to extend the allowable outage for them.
The [NRC) staff, therefore. recommends that an additional condition be established for the specific case. where 'One accumulator [SIT] is inoperable due to the inoperability of water level and pressure channels.' in which the completion time to restore the accumulator to operable status will be 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
While technically inoperable. the accumulator would be available to fulfill its safety function during this time and, thus, this change would have a negligible increase in risk."
(continued)
B 3.5.2-7 PALO VERDE UNITS 12,3 REVISION 1
SITs -
Shutdown B 3.5.2 BASES ACTIONS B.1 If one SIT is inoperable for a reason other than boron concentration or the inability to verify level or pressure the SIT must be returned to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
In this Condition, the required contents of three SITs cannot be assumed to reach the core during a LOCA.
CE NPSD-994 (Ref. 5) provides a series of deterministic and probabilistic findings that support 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> as being either risk beneficial" or "risk neutral" in comparison to shorter eriods for restoring the SIT to OPERABLE status. CE PSD-994 (Ref. 5) discusses best-estimate analysis for a typical PWR that confirmed that, during large-break LOCA scenarios, core melt can be prevented by either operation of one low pressure safety injection (LPSI) pump or the operation of one high pressure safety injection (HPSI) pump and a single SIT.
CE PSD-994 (Ref. 5) also discusses plant-specific probabilistic analysis that evaluated the risk-impact of the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> recovery period in comparison to shorter recovery periods.
C.1 If the inoperability of the required SIT was discovered but not restored while the plant was within the applicability of specification 3.5.1, "SITs - Operating", the plant must be brought to a MODE in which the LCO does not aply. The time allowed for restoration in specification 3.5.1 is adequate and may not be duplicated, for the same condition, when in specification 3.5.2, "SITs - Shutdown".
If the required SIT cannot be restored to OPERABLE status within the associated Completion Time, the plant must be brought to a MODE in which the LCO does not apply.
To achieve this status, the plant must be brought to at least MODE 5 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The allowed Completion Time is reasonable, based on operating experience, to reach the required plant conditions in an orderly manner and without challenging plant systems.
D.1 If more than one of the required SITs is inoperable, the unit is in a condition outside the accident analyses.
Therefore, LCO 3.0.3 must be entered immediately.
(continued)
PALO VED_NT EIIN2 PALO VERDE UNITS 1.2,3 B 3.5.2-8 REVISION 22
AC Sources - Operating B 3.8.1 B 3.8 ELECTRICAL POWER SYSTEMS B 3.8.1 AC Sources - Operating BASES BACKGROUND The unit Class 1E Electrical Power Distribution System AC sources consist of the offsite power sources (preferred power sources: normal and alternate(s)), and the onsite standby power sources (Train A and Train B diesel generators (DGs)). As required by 10 CFR 50. Appendix A, GDC 17 (Ref. 1), the design of the AC electrical power system provides independence and redundancy to ensure an available source of power to the Engineered Safety Features (ESF) systems.
The onsite Class 1E AC Distribution System is divided into redundant load groups (trains) so that the loss of any one group does not prevent the minimum safety functions from being performed. Each train has connections to two preferred offsite power sources (normal and alternate) and a single DG.
Offsite power is supplied to the unit switchyard from the transmission network by six transmission lines. From the switchyard, two electrically and physically separated circuits provide AC power, through ESF service transformers, to the 4.16 kV ESF buses. A detailed description of the offsite power network and the circuits to the Class 1E ESF buses is found in the updated FSAR, Chapter 8 (Ref. 2).
An offsite circuit consists of all breakers, transformers.
switches, interrupting devices, cabling, and controls required to transmit power from the offsite transmission network to the onsite Class 1E ESF bus or buses.
Certain required unit loads are returned to service in a predetermined sequence in order to prevent overloading the transformer (NBN-X03 and NBN-X04) supplying offsite power to the onsite Class lE Distribution System. Within 30 seconds after the initiating signal is received, all permanently connected and auto-connected emergency loads needed to recover the unit or maintain it in a safe condition are returned to service via the automatic load sequencer.
(continued)
PALO VERDE UNITS 1,2,3 I
B 3.8.1-1 REVISION 22
AC Sources -
Operating B 3.8.1 BASES BACKGROUND (continued)
The onsite standby power source for each 4.16 kV ESF bus is dedicated DG. DG-A and DG-B are dedicated to ESF buses PBA-S03 and PBB-S04. respectively. A DG starts automatically (in emergency mode) on a safety injection actuation signal (SIAS) (i.e.. low pressurizer pressure or high containment pressure signals), auxiliary feedwater actuation signals (AFAS-1 and AFAS-2) (e.g., low steam generator level), or on a loss of power (an ESF bus degraded voltage or undervoltage signal). After the DG has started, it will automatically tie to its respective bus after offsite power is tripped as a consequence of ESF bus undervoltage or degraded voltage, independent of or coincident with a SIAS or AFAS signal. Following the loss of offsite power, the sequencer sheds nonpermanent loads from the ESF bus. When the DG is tied to the ESF bus, loads are then sequentially connected to its respective ESF bus by the automatic load sequencer. The sequencing logic controls the permissive and starting signals to motor breakers to prevent overloading the G by automatic load application.
The DGs will also start and operate in the standby mode (running unloaded) without tying to the ESF bus on a SIAS or AFAS.
In the event of a loss of preferred power. the ESF electrical loads are automatically connected to the Gs in sufficient time to provide for safe reactor shutdown and to mitigate the consequences of a Design Basis Accident (BA) such as a loss of coolant accident (LOCA).
Certain required unit loads are returned to service in a predetermined sequence in order to prevent overloading the DG in the process. Within 40 seconds after the initiating signal is received, all loads needed to recover the unit or maintain it in a safe condition are returned to service.
Ratings for Train A and Train B DGs satisfy the requirements of Regulatory Guide 1.9 (Ref. 3).
The continuous service rating of each DG is 5500 kW with 10X overload permissible for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period. The ESF loads that are powered from the 4.16 kV ESF buses are listed in the updated FSAR. Chapter 8 (Ref. 2).
Offsite power sources must have the capability to effect a safe shutdown and to mitigate the effects of an accident as specified in Regulatory Guide 1.93 (Ref. 6).
As a result of (continued)
PALO VERDE UNITS 1,2,3 B 3.8.1-2 REVISION 2