ML073381136
| ML073381136 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 11/27/2007 |
| From: | Weber T Arizona Public Service Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 102-05768-TNW/CJS | |
| Download: ML073381136 (21) | |
Text
Technical Specification 5.5.14 Palo Verde Nuclear Generating Station Thomas N. Weber Department Leader Regulatory Affairs Tel. 623-393-5764 Fax 623-393-5442 Mail Station 7636 PO Box 52034 Phoenix, Arizona 85072-2034 102-05768-TNW/CJS November 27, 2007 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2 and 3 Docket Nos. STN 50-528/529/530 Technical Specifications Bases Revision 47 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 47, implemented on November 15, 2007.
The revision 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 Glenn Michael at (623) 393-5750.
Sincerely, Q,,AX 4ZJ~J.
TNW/GAM/CJS/gat A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway 0 Comanche Peak
- Diablo Canyon 0 Palo Verde 0 South Texas Project
- Wolf Creek Wiof mkJR
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Technical Specifications Bases Revision 47 Update Page 2 Enclosure - PVNGS Technical Specification Bases Revision 47 Insertion Instructions and Replacement Pages cc:
E. E. Collins Jr.
M. T. Markley G. G. Warnick NRC Region IV Regional Administrator (enclosure)
NRC NRR Project Manager (enclosure)
NRC Senior Resident Inspector for PVNGS (enclosure)
ENCLOSURE PVNGS Technical Specification Bases Revision 47 Insertion Instructions and Replacement Pages
Insertion Instructions for the Technical Specifications Bases Revision 47 REMOVE PAGES Cover page List of Effective Pages 1/2 through 7/8 B 3.1.2-7 / B 3.1.2-8 B 3.1.9-5 / B 3.1.9-6 B 3.3.1-15/ B 3.3.1-16 B 3.6.3-3 / B 3.6.3-4 INSERT PAGES Cover page List of Effective Pages 1/2 through 7/8 B 3.1.2-7 / B 3.1.2-8 B 3.1.9-5 / B 3.1.9-6 B 3.3.1-15/ B 3.3.1-16 B 3.6.3-3 / B 3.6.3-4 1
PVNGS Palo Verde Nuclear Generating Station Units 1, 2, and 3 Technical Specification Bases
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21 21 PALO VERDE UNITS 1, 2, AND 3 7
Revision 47 November 15, 2007
TECHNICAL SPECIFICATION BASES LIST OF EFFECTIVE PAGES Page No.
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AND 3 8
Revision 47 November 15, 2007
SDM - Reactor Trip Breakers Closed B 3.1.2 BASES ACTIONS A.1 (continued) concentrated solution, such as that normally found in the refueling water tank.
The operator should borate with the best source available for the plant conditions.
In determining the boration flow rate the time in core life must be considered.
For instance, the most difficult time in core life to increase the RCS boron concentration is at the beginning of cycle, when boron concentration may approach or exceed 2000 ppm.
Assuming that a value of 1%
AMk/k must be recovered and a boration flow rate of 26 gpm, it is possible to increase the boron concentration of the RCS by 100 ppm in less than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> with a 4000 ppm source.
If a boron worth of 10 pcm/ppm is assumed, this combination of parameters will increase the SDM by 1% Ak/k.
These boration parameters of 26 gpm and 4000 ppm represent typical values and are provided for the purpose of offering a specific example.
B.1 and B.2 If the KN-1 requirements are not met or reactor criticality is achievable by Shutdown Group CEA movement, boration must be initiated promptly and CEA position varied to restore KN_1 within limit or to ensure criticality due to Shutdown Group CEA movement is not achievable.
A Completion Time of 15 minutes is adequate for an operator to correctly align and start the required systems and components and vary CEA position.
It is assumed that boration will be continued and CEA position varied to return KN-1 to within limit or prevent reactor criticality due to Shutdown Group CEA movement.
CEA movement is only required if the specific limit exceeded can be improved by taking this action.
In the determination of the required combination of boration flow rate and boron concentration, there is no unique requirement that must be satisfied.
Since it is imperative to raise the boron concentration of the RCS as soon as possible, the boron concentration should be a highly concentrated solution, such as that normally found in the refueling water tank.
The operator should borate with the best source available for the plant conditions.
(continued)
PALO VERDE UNITS 1,2,3 B 3.1.2-7 REVISION 12
SDM - Reactor Trip Breakers Closed B 3.1.2 BASES ACTIONS B.1 and B.2 (continued)
In determining the boration flow rate the time in core life must be considered.
For instance, the most difficult time in core life to increase the RCS boron concentration is at the beginning of cycle, when the boron concentration will exceed 2000 ppm.
Assuming that a value of 1% Ak/k must be recovered and.a boration flow rate of 26 gpm, it is possible to increase the boron concentration of the RCS by 100 ppm in less than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> with a 4000 ppm source.
If a boron worth of 10 pcm/ppm is assumed, this combination of parameters will increase the SDM by 1% Ak/k.
These boration parameters of 26 gpm and 4000 ppm represent typical values and are provided for the purpose of offering a specific example.
SURVEILLANCE SR 3.1.2.1, 3.1.2.2 and 3.1.2.3 REQUIREMENTS
- SDM, KN-1, and criticality not being achievable with Shutdown Group CEA withdrawal are verified by performing a reactivity balance calculation, considering the listed reactivity effects:
- a.
- b.
CEA positions;
- c.
RCS average temperature;
- d.
Fuel burnup based on gross thermal energy generation;
- e.
Xenon concentration;
- f.
Samarium concentration; and
- g.
Isothermal temperature coefficient (ITC).
Using the ITC accounts for Doppler reactivity in this calculation because the reactor is subcritical, and the fuel temperature will be changing at the same rate as that of the RCS.
(continued)
PALO VERDE UNITS 1,2,3 B 3.1.2-8 REVISION 47
STE-SDM B 3.1.9 BASES (continued)
ACTIONS A. 1 With any CEA not fully inserted and less than the minimum required reactivity equivalent available for insertion, or with all CEAs inserted and the reactor subcritical by less than the reactivity equivalent of the highest worth withdrawn CEA, restoration of the minimum shutdown reactivity requirements must be accomplished by increasing the RCS boron concentration.
The required Completion Time of 15 minutes for initiating boration allows the operator sufficient time to align the valves and start the boric acid pumps and is consistent with the Completion Time of LCO 3.1.2.
In the determination of the required combination of boration flow rate and boron concentration, there is no unique requirement that must be satisfied.
Since it is imperative to raise the boron concentration of the RCS as soon as possible, the boron concentration should be a highly concentrated solution, such as that normally found in the refueling water tank.
The operator should borate with the best source available for the plant conditions.
In determining the boration flow rate the time in core life must be considered.
For instance, the most difficult time in core life to increase the RCS boron concentration is at the beginning of cycle, when boron concentration may approach or exceed 2000 ppm.
Assuming that a value of 1%
Ak/k must be recovered and a boration flow rate of 26 gpm, it is possible to increase the boron concentration of the RCS by 100 ppm in less than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> with a 4000 ppm source.
If a boron worth of 10 pcm/ppm is assumed, this combination of parameters will increase the SDM by 1% Ak/k.
These boration parameters of 26 gpm and 4000 ppm represent typical values and are provided for the purpose of offering a specific example.
SURVEILLANCE SR 3.1.9.1 REQUIREMENTS Verification of the position of each partially or fully withdrawn full strength, part length, or part strength CEA is necessary to ensure that the minimum negative reactivity requirements for insertion on a trip are preserved.
A 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Frequency is sufficient for the operator to verify that each CEA position is within the acceptance criteria.
(continued)
PALO VERDE UNITS 1,2,3 B 3.1.9-5 REVISION 47
STE-SDM B 3.1.9 BASES (continued)
SR 3.1.9.2 Prior demonstration that each CEA to be withdrawn from the core during PHYSICS TESTS is capable of full insertion, when tripped from at least a 50% withdrawn position, ensures that the CEA will insert on a trip signal.
The 7 day Frequency ensures that the CEAs are OPERABLE prior to reducing SDM requirements to less than the limits of LCO 3.1.2.
SR 3.1.9.3 During MODE 3, verification that the reactor is subcritical by at least the reactivity equivalent of the highest estimated CEA worth ensures that the minimum negative reactivity requirements are preserved.
The negative reactivity requirements are verified by performing a reactivity balance calculation, considering the listed reactivity effects:
- a.
- b.
CEA positions;
- c.
RCS average temperature;
- d.
Fuel burnup based on gross thermal energy generation;
- e.
Xenon concentration; and
- f.
Samarium concentration.
The Frequency of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> is based on the generally slow change in required boron concentration, and it allows sufficient time for the operator to collect the required data.
REFERENCES
- 1.
10 CFR 50, Appendix B, Section XI.
- 2.
- 3.
Regulatory Guide 1.68, Revision 2, August 1978.
- 4.
ANSI/ANS-19.6.1-1985, December 13, 1985.
- 5.
UFSAR, Chapter 14.
- 6.
- 7.
UFSAR, Chapter 15.
PALO VERDE UNITS 1,2,3 B 3.1.9-6 REVISION 1
RPS Instrumentation - Operating B 3.3.1 BASES BACKGROUND RPS Logic (continued)
The matrix relay contacts are arranged into trip paths, with one of the four matrix relays in each matrix opening contacts in one of the four trip paths.
Each trip path provides power to one of the four normally energized RTCB initiation relays.
The trip paths thus each have six contacts in series, one from each matrix, and perform a logical OR function, opening the RTCBs if any one or more of the six T-gic matrices indicate a coincidence condition.
Each trip path is responsible for opening one of the four RTCBs.
The RTCB initiation relays, when de-energized, interrupt power to the breaker undervoltage trip attachments and simultaneously apply power to the shunt trip attachments on each of the breakers.
Actuation of either the undervoltage or shunt trip attachment is sufficient to open the RTCB and interrupt power from the motor generator (MG) sets to the control element drive mechanisms (CEDMs).
When a coincidence occurs in two RPS channels, all four matrix relays in the affected matrix de-energize.
This in turn de-energizes all four initiation relays, which simultaneously de-energize the undervoltage and energize the shunt trip attachments in all four RTCBs, tripping them open.
Matrix Logic refers to the matrix power supplies, trip channel bypass contacts, and interconnecting matrix wiring between bistable relay cards, up to but not including the matrix relays.
Matrix contacts on the bistable relay cards are excluded from the Matrix Logic definition, since they are addressed as part of the measurement channel.
The Initiation Logic consists of the trip path power source, matrix relays and their associated contacts, all interconnecting wiring, initiation relays, and the initiation relay contacts in the RTCB control circuitry.
(continued)
PALO VERDE UNITS 1,2,3 B 3.3.1-15 REVISION 35
RPS Instrumentation - Operating B 3.3.1 BASES BACKGROUND RPS Logic (continued)
It is possible to change the two-out-of-four RPS Logic to a two-out-of-three logic for a given input parameter in one channel at a time by trip channel bypassing select portions of the Matrix Logic.
Trip channel bypassing a bistable effectively shorts the bistable relay contacts in the three matrices associated with that channel.
Thus, the bistables will function normally, producing normal trip indication and annunciation, but a reactor trip will not occur unless two additional channels indicate a trip condition.
Trip channel bypassing can be simultaneously performed on any number of parameters in any number of channels, providing each parameter is bypassed in only one channel at a time.
An interlock prevents simultaneous trip channel bypassing of the same parameter in more than one channel.
Trip channel bypassing is normally employed during maintenance or testing.
Two-out-of-three logic also prevents inadvertent trips caused by any single channel failure in a trip condition.
In addition to the trip channel bypasses, there are also operating bypasses on select RPS trips.
These bypasses are enabled manually in all four RPS channels when plant conditions do not warrant the specific trip protection.
All operating bypasses are automatically removed when enabling bypass conditions are no longer satisfied.
Operating bypasses are normally implemented in the bistable, so that normal trip indication is also disabled.
Trips with operating bypasses include Pressurizer Pressure -
Refer also to B 3.3.5 for ESFAS operating bypasses.
Reactor Trip Circuit Breakers (RTCBs)
The reactor trip switchgear, addressed in LCO 3.3.4, consists of four RTCBs.
Power input to the reactor trip switchgear comes from two full capacity MG sets operated in parallel, such that the loss of either MG set does not de-energize the CEDMs.
Power is supplied from the MG sets to the CEDM's via two redundant paths (trip legs).
Trip legs 1 and 3 are in parallel with Trip legs 2 and 4.
This ensures that a fault or the opening of a breaker in one trip leg (i.e., for testing purposes) will not interrupt power to the CEDM buses.
(continued)
PALO VERDE UNITS 1,2,3 B 3.3.1-16 REVISION 35
Containment Isolation Valves B 3.6.3 BASES APPLICABLE The containment isolation valve LCO was derived from the SAFETY ANALYSES assumptions related to minimizing the loss of reactor coolant inventory and establishing the containment boundary during major accidents.
As part of the containment boundary, containment isolation valve OPERABILITY supports leak tightness of the containment.
Therefore, the safety analysis of any event requiring isolation of containment is applicable to this LCO.
The DBAs that result in a release of radioactive material within containment are a Loss Of Coolant Accident (LOCA),
a Main Steam Line Break (MSLB),
a feedwater line break, and a control element assembly ejection accident.
In the analysis for each of these accidents, it is assumed that containment isolation valves are either closed or function to close within the required isolation time following event initiation.
This ensures that potential paths to the environment through containment isolation valves (including containment purge valves) are minimized.
The safety analysis assumes that the refueling purge valves are closed at event initiation.
The DBA analysis assumes that, within 60 seconds after the accident, isolation of the containment is complete and leakage terminated except for the design leakage rate, La.
The power access purge valves are assumed to close within 12 seconds of the DBA.
The containment isolation response time includes signal delay, diesel generator startup (for loss of offsite power), and containment isolation valve stroke times.
The single failure criterion required to be imposed in the conduct of unit safety analyses was considered in the original design of the containment purge valves.
Two valves in series on each purge line provide assurance that both the supply and exhaust lines could be isolated even if a single failure occurred.
The inboard and outboard isolation valves on each line are provided with diverse power sources.
The refueling purge valves may be unable to close in the environment following a LOCA.
Therefore, each of the refueling purge valves is required to remain sealed closed during MODES 1, 2, 3, and 4 or the flow paths of the refueling purge valves are required to be isolated with blind flanges.
In this case, the single failure criterion remains applicable to the containment refueling purge valves due to failure in the control circuit associated with each valve.
Again, the purge system valve design precludes a single failure from compromising the containment boundary as long as the system is operated in accordance with the subject LCO.
(continued)
PALO VERDE UNITS 1.2,3 B 3.6.3-3 REVISION 47
Containment Isolation Valves B 3.6.3 BASES APPLICABLE The power access purge valves are capable of closing under SAFETY ANALYSES accident conditions.
Therefore, they are allowed to be open (continued) for limited periods during power operation.
The OPERABILITY of main steam safety valves, main steam isolation valves, main feedwater isolation valves, and main steam atmospheric dump valves is covered by Specifications 3.7.1, 3.7.2, 3.7.3 and 3.7.4 respectively.
The containment isolation valves satisfy Criterion 3 of 10 CFR 50.36 (c)(2)(ii).
LCO Required containment isolation valves, (CIVs) form a part of the containment boundary.
A containment penetration is considered to be the area bounded by the inboard and outboard CIVs and includes all valves, piping, and connections within this boundary (e.g., vents, drains, and test connections)
(Ref. 7).
The containment isolation valve safety function is related to minimizing the loss of reactor coolant inventory and establishing the containment boundary during a DBA.
The automatic power operated isolation valves are required to have isolation times within limits and to actuate on an automatic isolation signal.. The refueling purge valves must be maintained sealed closed.
All manual vent, drain, and test valves within a Containment Penetration (i.e., between the Containment Isolation Valves) will be maintained locked closed per the locked valve administrative program or surveilled closed per Technical Specification SR 3.6.3.3 or SR 3.6.3.4.
The valves covered by this LCO are listed with their associated stroke times in the UFSAR (Ref. 1).
The analyses assume the containment is isolated within 60 seconds following an isolation signal (CIAS).
All containment isolation valves are considered to be required except for each 42 inch refueling purge valve when its flow path is isolated with a blind flange tested in accordance with SR 3.6.1.1 as allowed by Note 5 under LCO 3.6.3.
This is allowed because the blind flange, instead of the valve, provides the function of the containment boundary.
Required CIVs are considered OPERABLE for LCO 3.6.3 when they are closed (i.e., manual valves are closed, automatic valves are de-activated and secured in their closed position), blind flanges are in place, and closed systems are intact.
The Steam Generating System and the Containment Pressure Monitoring System are the only credited closed systems at PVNGS.
Placement of CIVs in this configuration may impact the operability of the associated system.
If the required valve surveillances have lapsed for a CIV secured in its closed (continued)
PALO VERDE UNITS 1,2,3 B 3.6.3-4 REVISION 43