ML13217A054

Enclosure 1 - Technical Specifications Bases, Revision 58

ML13217A054
Person / Time
Site:	Palo Verde
Issue date:	07/03/2013
From:	Stephenson C Arizona Public Service Co
To:	Office of Nuclear Reactor Regulation
References
102-06731-TNW/RKR/CJS
Download: ML13217A054 (26)

Text

PVNGS Technical Specification Bases (TS Bases)

Revision 58 Replacement Pages and Insertion Instructions The following LDCRs are included in this change:

LDCR 11-B002 reflects changes approved by NRC License Amendment 191, dated April 11, 2013, related to TS Bases Section 3.7.4, Atmospheric Dump Valves (ADVs), that requires four ADV lines be OPERABLE when in Modes 1,2, 3, and in Mode 4 when the steam generators are being used for heat removal.

Related LDCR 07-R002 removes similar requirements for ADV operability that had been included in the Technical Requirements Manual (TRM) as an interim action, until the license amendment was approved.

LDCR 12-B006 clarified TS Bases Sections 3.4.8, RCS Loops- MODE 5, Loops Not Filled, and 3.9.5, SDC and Coolant Circulation - Low Water Level, to indicate that Containment Spray (CS) pumps are not to be used for normal operations if the water level is at or below the top of the hot-leg pipe (103' - 1") due to concerns of potential air entrainment and gas binding of the CS pump. The LDCR also updated the Reference section of the Bases for each specification.

Instructions Remove Paqe: InsertNew Paqe:

Cover Page Cover Page List of EffectivePages List of Effective Pages 1/2 through 7/8 1/2 through 9/Blank B 3.4.8-1 B 3.4.8-2 B 3.4.8-1/ B 3.4.8-2 B 3.4.8-3 Blank B 3.4.8-3/ B 3.4.8-4 B 3.7.4-1 B 3.7.4-2 B 3.7.4-1 / B 3.7.4-2 through through B 3.7.4-5 Blank B 3.7.4-5 / B 3.7.4-6 B 3.9.5-1 B 3.9.5-2 B 3.9.5-1 / B 3.9.5-2 B 3.9.5-3 B 3.9.5-4 B 3.9.5-3 / B 3.9.5-4 Digitally signed by Stephenson, Carl Stephenson, J(Z05778)

DN: cn=Stephenson, Carl J(Z05778)

Carl J(Z05778)

Reason: I attest to the accuracy and integrity of this document Date: 2013.06.28 09:53:27 -07'00'

PVNGS Palo Verde Nuclear Generating Station Units 1, 2, and 3 Technical Sp eclficatlon Bases Revision 58 July 03, 2013

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Date: 20 !3.06.28 09:16:17 -07'00'

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B 2 1 i-i 0 B 3 1 3-2 0 B 2 1 i-2 0 B 3 1 3-3 0 B 2 1 i-3 37 B 3 1 3-4 0 B 2 1 i-4 21 B 3 1 3-5 0 B 2 1 i-5 54 B 3 1 3-6 56 B 2 1 2-I 0 B 3 1 4-i 0 B 2 1 2-2 31 B 3 1 4-2 31 B 2 1 2-3 0 B 3 1 4-3 0 B 2 1 2-4 54 B 3 1 4-4 0 B 3 0-i 49 B 3 1 4-5 0 B 3 0-2 0 B 3 1 5-i 0 B 3 0-3 0 B 3 1 5-2 52 B 3 0-4 0 B 3 1 5-3 52 B 3 0-5 42 B 3 1 5-4 52 B 3 0-6 48 B 3 1 5-5 52 B 3 0-7 48 B 3 1 5-6 52 B 3 0-8 42 B 3 1 5-7 52 B 3 0-9 42 B 3 1 5-8 52 B 3 0-i0 42 B 3 1 5-9 52 B 3 0-ii 42 B 3 1 5-10 56 B 3 0-12 42 B 3 1 5-11 56 B 3 0-13 42 B 3 1 5-12 56 B 3 0-14 49 B 3 1 6-i 0 B 3 0-15 50 B 3 1 6-2 46 B 3 0-16 50 B 3 1 6-3 42 B 3 0-17 50 B 3 1 6-4 42 B 3 0-18 49 B 3 1 6-5 56 B 3 0-19 49 B 3 1 6-6 46 B 3 0-20 49 B 3 1 7-i 57 B 3 0-21 49 B 3 1 7-2 0 B 3 0-22 49 B 3 1 7-3 53 B 3 1 i-I 28 B 3 1 7-4 48 B 3 1 i-2 0 B 3 1 7-5 25 B 3 1 i-3 43 B 3 1 7-6 0 B 3 1 i-4 43 B 3 1 7-7 0 B 3 1 I-5 27 B 3 1 7-8 56 B 3 1 i-6 56 B 3 1 7-9 56 B 3 1 2-I 28 B 3 1 8-i 52 B 3 1 2-2 0 B 3 1 8-2 52 B 3 1 2-3 43 B 3 1 8-3 52 B 3 1 2-4 28 B 3 1 8-4 52 B 3 1 2-5 0 B 3 1 8-5 56 B 3 1 2-6 43 B 3 1 9-i 0 B 3 1 2-7 12 B 3 1 9-2 0 B 3 1 2-8 47 B 3 1 9-3 0 B 3 1 2-9 56 B 3 1 9-4 0 B 3 1 3-I 0 B 3 1 9-5 56 PALO VERDE UNITS i, 2, AND 3 1 Revision 58 July 03, 2013

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B 3 4 5-3 38 B 3 4 13-8 52 B 3 4 5-4 56 B 3 4 13-9 56 B 3 4 5-5 56 B 3 4 13-I0 56 B 3 4 6-i 0 B 3 4 13-ii 55 B 3 4 6-2 6 B 3 4 14-i 0 B 3 4 6-3 52 B 3 4 14-2 34 B 3 4 6-4 6 B 3 4 14-3 34 B 3.4 6-5 56 B 3 4 14-4 38 B 3.4 7-i 0 B 3 4 14-5 38 B 3.4 7-2 6 B 3 4 14-6 38 B 3.4 7-3 52 B 3 4 14-7 56 B 3.4 7-4 54 B.3 4 14-8 56 B 3.4 7-5 0 B 3 4 15-i 0 B 3.4 7-6 56 B 3 4 15-2 48 B 3.4 7-7 52 B 3 4 15-3 0 B 3.4 8-i 0 B 3 4 15-4 0 B 3.4 8-2 58 B 3 4 15-5 56 B 3.4 8-3 58 B 3 4 15-6 56 B 3.4 8-4 58 B 3 4 15-7 54 B 3.4 9-i 41 B 3 4 16-i 2 B 3.4 9-2 31 B 3 4 16-2 i0 B 3.4 9-3 41 B 3 4 16-3 0 B 3.4 9-4 41 B 3 4 16-4 42 B 3.4 9-5 56 B 3 4 16-5 56 B 3.4 9-6 56 B 3 4 16-6 56 B 3.4 i0-I 53 B 3 4 17-i 0 B 3.4 I0-2 7 B 3 4 17-2 27 B 3.4 i0-3 0 B 3 4 17-3 42 B 3 4 i0-4 54 B 3 4 17-4 42 B 3 4 Ii-i 0 B 3 4 17-5 57 B 3 4 ii-2 53 B 3 4 17-6 56 B 3 4 ii-3 0 B 3 4 18-i 38 B 3 4 11-4 52 B 3 4 18-2 40 B 3 4 11-5 56 B 3.4 18-3 38 B 3 4 11-6 54 B 3 4 18-4 38 B 3 4 12-i 1 B 3 4 18-5 38 B 3 4 12-2 34 B 3 4 18-6 38 B 3 4 12-3 48 B 3 4 18-7 38 B 3 4 12-4 56 B 3 4 18-8 38 B 3 4 12-5 31 B 3 5 i-i 0 B 3 4 13-i 0 B 3 5 i-2 53 B 3 4 13-2 55 B 3 5 i-3 7 B 3 4 13-3 55 B 3 5 i-4 0 B 3 4 13-4 52 B 3 5 i-5 0 B 3 4 13-5 55 B 3 5 i-6 0 B 3 4 13-6 55 B 3 5 i-7 1 B 3 4 13-7 52 B 3 5 I-8 1 PALO VERDE UNITS i, 2, AND 3 5 Revision 58 July 03, 2013

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B 3.7 2-2 42 B 3 7 I0-2 1 B 3 7 2-3 40 B 3 7 i0-3 1 B 3 7 2-4 40 B 3 7 i0-4 56 B 3 7 2-5 40 B 3 7 ii-i 50 B 3 7 2-6 40 B 3 7 ii-2 50 B 3 7 2-7 40 B 3 7 ii-3 51 B 3 7 2-8 54 B 3 7 ii-4 55 B 3 7 2-9 54 B 3 7 ii-5 50 B 3.7 3-i 1 B 3 7 ii-6 55 B 3.7 3-2 1 B 3 7 ii-7 57 B 3.7 3-3 37 B 3 7 ii-8 56 B 3.7 3-4 0 B 3 7 ii-9 50 B 3 7 3-5 54 B 3 7 12-i 1 B 3 7 4-i 58 B 3 7 12-2 21 B 3 7 4-2 58 B 3 7 12-3 55 B 3 7 4-3 58 B 3 7 12-4 56 B 3 7 4-4 58 B 3 7 13-i 0 B 3 7 4-5 58 B 3 7 13-2 0 B 3.7 4-6 58 B 3 7 13-3 0 B 3.7 5-i 0 B 3 7 13-4 57 B 3.7 5-2 0 B 3 7 13-5 56 B 3.7 5-3 40 B 3 7 14-i 0 B 3.7 5-4 27 B 3 7 14-2 21 B 3.7 5-5 42 B 3 7 14-3 56 B 3.7 5-6 42 B 3 7 15-I 3 B 3 7 5-7 9 B 3 7 15-2 56 B 3 7 5-8 56 B 3 7 16-i 7 B 3 7 5-9 56 B 3 7 16-2 0 B 3 7 5-i0 56 B 3.7 16-3 56 B 3 7 5-ii 54 B 3.7 16-4 0 B 3 7 6-i 54 B 3.7 17-i 52 B 3 7 6-2 54 B 3.7 17-2 3 B 3 7 6-3 55 B 3.7 17-3 3 B 3 7 6-4 56 B 3.7 17-4 3 B 3 7 7-i 0 B 3.7 17-5 3 B 3 7 7-2 1 B 3.7 17-6 52 B 3 7 7-3 1 B 3 8 I-I 35 B 3 7 7-4 56 B 3 8 I-2 2 B 3 7 7-5 56 B 3 8 I-3 34 B 3 7 8-i 1 B 3 8 i-4 34 B 3 7 8-2 1 B 3 8 i-5 20 B 3 7 8-3 1 B 3 8 I-6 57 B 3 7 8-4 56 B 3 8 i-7 42 B 3 7 9-I 0 B 3 8 I-8 50 B 3 7 9-2 44 B 3 8 i-9 42 B 3 7 9-3 56 B 3 8 i-i0 43 B 3 7 i0-i i0 B 3 8 i-ii 50 PALO VERDE UNITS i, 2, AND 3 7 Revision 58 July 03, 2013

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This page intentionally blank RCSLoops- MODE 5, LoopsNot Filled B 3.4.8 B 3.4 REACTOR COOLANT SYSTEM(RCS)

B 3.4.8 RCSLoops - MODE5, Loops Not Filled BASES BACKGROUND In MODE5 with the RCSloops not filled, the primary function of the reactor coolant is the removal of decay heat and transfer of this heat to the Shutdown Cooling (SDC) heat exchangers. The Steam Generators (SGs) are not available as a heat sink when the loops are not filled. The secondary function of the reactor coolant is to act as a carrier for the soluble neutron poison, boric acid.

In MODE5 with loops not filled, only the SDCSystem can be used for coolant circulation. The number of trains in operation can vary to suit the operational needs. The intent of this LCOis to provide forced flow from at least one SDCtrain for decay heat removal and transport and to require that two paths be available to provide redundancy for heat removal.

APPLICABLE In MODE5, RCScirculation is considered in determining SAFETYANALYSES the time available for mitigation of the accidental boron dilution event. The SDCtrains provide this circulation.

The flow provided by one SDCtrain is adequate for decay heat removal and for boron mixing.

RCSloops - MODE5 (loops not filled) have been identified in 10 CFR50.36 (c)(2)(ii) as important contributors to risk reduction.

LCO The purpose of this LCO is to require a minimum of two SDC trains be OPERABLE and one of these trains be in operation.

An OPERABLE train is one that is capable of transferring heat from the reactor coolant at a controlled rate. Heat cannot be removed via the SDCSystem unless forced flow is used. A minimum of one running SDCpump meets the LCO requirement for one train in operation. An additional SDC train is required to be OPERABLE to meet the single failure criterion.

(continued)

PALOVERDEUNITS 1,2,3 B 3.4.8-1 REVISION0

RCSLoops- MODE 5, Loops Not Filled B 3.4.8 BASES (continued)

LCO Note 1 permits all SDCpumpsto be de-energized _ 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per (continued) 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period. The circumstances for stopping both SDCpumps are to be limited to situations when the outage time is short and the core outlet temperature is maintained > IO°F below saturation temperature. The 10 degrees F is considered the actual value of the necessary difference between RCScore outlet temperature and the saturation temperature associated with RCSpressure to be maintained during the time the pumps would be de-energized. The instrument error associated with determining this difference is less than 10 degrees F. (There are no special restrictions for instrumentation use.)

Therefore, the indicated value of the difference between RCS core outlet temperature and the saturation temperature associated with RCSpressure must be greater than or equal to i allowing 20 degreestheF pumpsto in order beto de-energized, (Ref. of1) theThe use the provisions Note Note prohibits boron dilution or draining operations when SDC forced flow is stopped.

Note 2 allows one SDCtrain to be inoperable for a period of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> provided that the other train is OPERABLE and in operation. This permits periodic surveillance tests to be performed on the inoperable train during the only time when these tests are safe and possible.

An OPERABLE SDCtrain is composed of an OPERABLE SDCpump (CS or LPSI) capable of providing flow to the SDCheat exchanger for heat removal. SDCpumpsare OPERABLE if they are capable of being powered and are able to provide flow, if required. Note that the CS pumps shall not be used for normal operations if the water level is at or below the top of the hot-leg pipe (103' 1") due to concerns of potential air entrainment and gas binding of the CS pump (Ref, 2).

APPLICABILITY In MODE5 with loops not filled, this LCOrequires core heat removal and coolant circulation by the SDCSystem.

Operation in other MODESis covered by:

LCO3.4.4, "RCSLoops-MODES1 and 2";

LCO3.4.5, "RCSLoops - MODE3";

LCO 3.4.6, "RCSLoops - MODE4";

LCO 3.4,7, "RCSLoops - MODE5, Loops Filled";

LCO3.9.4, "Shutdown Cooling (SDC) and Coolant Circulation - High Water Level" (MODE6); and (continued)

PALOVERDEUNITS 1,2,3 B 3.4.8-2 REVISION58

RCSLoops - MODE5, Loops Not Filled B 3,4.8 BASES (continued)

APPLICABILITY LCO3.9.5, "ShutdownCooling (SDC)and Coolant (continued) Circulation - LowWater Level" (MODE 6),

ACTIONS A.I If a SDCtrain is inoperable, redundancy for heat removal is lost. Action must be initiated immediately to restore a second train to OPERABLE status. The Completion Time reflects the importance of maintaining the availability of two paths for heat removal.

B.1 and B.2 If no SDCtrain is OPERABLE or in operation, except as provided in NOTEI, all operations involving the reduction of RCSboron concentration must be suspended. Action to restore one SDCtrain to OPERABLE status and operation must be initiated immediately. Boron dilution requires forced circulation for proper mixing and the margin to criticality must not be reduced in this type of operation. The immediate Completion Time reflects the importance of maintaining operation for decay heat removal.

SURVEILLANCE SR 3.4.8.1 REQUIREMENTS This SR requires verification that one SDCtrain is in operation and circulating reactor cool ant at a flow rate of greater than or equal to 3780 gpm. Verification includes flow rate, temperature, or pump status monitoring, which help ensure that forced flow is providing decay heat removal. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.4.8.2 Verification that the required number of trains are OPERABLE ensures that redundant paths for heat removal are available and that an additional train can be placed in operation, if needed, to maintain decay heat removal and reactor coolant circulation. Verification is performed by verifying proper breaker alignment and indicated power available to the required pumps. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

(continued)

PALOVERDEUNITS 1,2,3 B 3.4.8-3 REVISION58

RCSLoops - MODE 5, Loops Not Filled B 3.4.8 BASES (continued)

REFERENCES 1. PVNGSCalculation 13-JC-SH-0200, Section 2.9.

2. PVNGSCalculation 13-MC-SI-0250, Appendix C.

PALOVERDEUNITS 1,2,3 B 3.4.8-4 REVISION58

ADVs B 3,7.4 B 3.7 PLANTSYSTEMS B 3.7,4 Atmospheric DumpValves (ADVs)

BASES BACKGROUND The ADVsprovide a safety grade method for cooling the unit to Shutdown Cooling (SDC) System entry conditions, should the preferred heat sink via the Steam Bypass Control System (SBCS) to the condenser and/or atmosphere not be available, as discussed in the UFSAR,Section 10.3 (Ref. 1). The ADVs have the capacity to achieve and maintain safe shutdown conditions following design basis accidents involving a loss of offsite power and/or closure of the Main Steam Isolation Valves (MSIVs) following receipt of a Main Steam Isolation Signal (MSIS). This is done in conjunction with the Auxiliary Feedwater System providing cooling water from the Condensate Storage Tank (CST). The ADVsmay also be required to meet the design cooldown rate during a normal cooldown.

Four ADV lines are provided. Each ADV line consists of one normally closed ADVand an associated, normally open block valve. Two ADV lines per steam generator are required to meet the single failure assumptions following a design basis accident that may render one steam generator (SG) unavailable for heat removal. The ADV block valves permit testing of the ADVswhile a unit is at power. The safety analyses, however, do not credit block valve operation as a meansof isolation of a failed open ADV.

The ADVsare equipped with pneumatic controllers to permit control of the cooldown rate.

The ADVsare provided with a pressurized gas supply of bottled nitrogen that, on a loss of pressure in the normal instrument air supply, automatically supplies nitrogen to operate the ADVs. The nitrogen supply is sized to provide sufficient pressurized gas to operate the ADVsfor the time required for Reactor Coolant System (RCS) cooldown to the Shutdown Cooling (SDC) System entry conditions, as described in UFSARAppendix 5C, "Natural Circulation Cooldown Analysis." The Appendix 5C analysis is based on the assumptions and conditions in the NRC's Branch Technical Position (BTP) RSB5-1, "Design Requirements of the Residual Heat Removal System." RSB5-I is an attachment (continued)

PALOVERDEUNITS1,2,3 B 3.7.4-1 REVISION58

ADVs B 3.7.4 BASES BACKGROUND (continued) to Standard Review Plan (SRP) 5.4.7, "Residual Heat Removal (RHR) System," and identifies RHRSystem requirements that ensure conformance with General Design Criteria (GDC) 34, "Residual Heat Removal."

The PVNGSRSB5-1 cooldown scenario described in UFSAR Appendix 5C is based on a natural circulation cooldown with both steam generators (SGs) available, using safety-grade equipment, assuming a loss of offsite power, a limiting single failure (assumed to be a diesel generator failure),

and with minimal operator actions outside the control room, as approved by the NRC. The RSB5-1 cooldown duration was established during actual testing performed in January 1986, and was confirmed through subsequent analyses to address steam generator replacement and power uprates.

A description of the ADVs is found in Reference 1. The ADVs require both Direct Current (DC) sources and class Alternating Current (AC) instrument power to be considered OPERABLE. In addition, non-safety related hand wheels are provided for local manual operations although hand wheels are not required for ADVOPERABILITYor credited in the accident analysis.

APPLICABLE The design basis of the ADVs is established by the SAFETYANALYSES capability to cool the unit to SDCSystem entry conditions.

The design must also accommodatecredible single failures that may render as many as two ADVs (i.e., one on each steam generator) incapable of opening on demand. This design is adequate to cool the unit to SDCSystem entry conditions with only one ADVand one SG, utilizing the cooling water supply available in the CST. Cooldown scenarios using a single ADVmay require a combination of the available nitrogen supply and local manual operation or other actions.

Alternatives for cooldown and for ADV operation beyond the RSB5-1 scenario have been evaluated using probabilistic risk analysis (PRA) as part of the resolution of Unresolved Safety Issue (USI) A-45, "Shutdown Decay Heat Removal Requirements." USI A-45 was subsumed into the Individual Plant Examination (IPE) which used PRAtechniques and was submitted to the NRCin response to Generic Letter 88-20.

The IPE considered various operator actions and the use of non-safety related equipment, and concluded that there are no significant heat removal vulnerabilities at PVNGS.

(continued)

PALOVERDEUNITS 1,2,3 B 3.7.4-2 REVISION58

ADVs B 3.7.4 BASES APPLICABLE SAFETYANALYSES Operator actions to locally operate the ADVs are not credited (continued) in the UFSARChapter 15 accident analyses but are described in the EOPs; non-safety related equipment such as the supplemental nitrogen supply could also be used during extended cooldown situations.

The design basis accident analyses also account for a single failure that may render one ADV incapable of being closed remotely, after it is opened by control room operators. This type of postulated failure yields more adverse radiological consequences for certain analyses, because it creates a pathway for radioisotope discharges to the environment. For accident mitigation the safety analyses do not credit isolation of a failed open ADV by either local manual hand wheel operation or closure of its associated block valve.

The safety analyses in the UFSARassume that plant operators will use the ADVsto cool down an affected unit to SDCSystem entry conditions, following accidents accompanied by a loss of offsite power and/or closure of the MSIVs. Initiation of operator action is typically assumed to occur 30 minutes following the initiation of an event; however, to conservatively bound maximumpotential dose consequences for Steam Generator Tube Rupture (SGTR) events, initiation of this operator action is assumed to occur two minutes following reactor trip. Prior to the operator action, the Main Steam Safety Valves (MSSVs)are credited in the analyses to maintain SG pressure and temperature near the MSSVsetpoints.

The limiting design basis event for nitrogen supply capacity is the RSB5-1 natural circulation cooldown scenario described above. This scenario includes an initial period of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at hot standby conditions followed by natural circulation cooldown for 9.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> until SDCentry conditions are achieved. Each ADV is required to have a nitrogen supply that supports ADV operation for a total of 13.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, Limiting design basis accidents with respect to RCSheat removal and ADVsteam flow capacity include those that may render one SG unavailable, with a coincident loss of offsite power and a single active component failure (i.e.,

main steam line breaks upstream of the MSIVs, and feedwaterline breaks).

(continued)

PALOVERDEUNITS 1,2,3 B 3.7.4-3 REVISION58

ADVs B 3.7.4 BASES APPLICABLE SAFETYANALYSES The limiting design basis event with respect to offsite (continued) radiological consequences is a SGTRwith a coincident loss of offsite power, a coincident RCSiodine spike, and a single failed open ADVon the affected SG (SGTRLOPSF). To determine bounding radiological consequences, an ADV is assumed to stick open during operator action that occurs two minutes after trip, and remains open for the duration of the cooldown. For this SGTRLOPSF case, plant operators will direct auxiliary feedwater flow to the affected SG after the accident has occurred. The steam released through the ADVsis contaminated, however, because of primary-to-secondary leakage that transports radioisotopes from the RCSto the SG.

The ADVssatisfy Criterion 3 of 10 CFR50.36 (c)(2)(ii).

LCO Four ADV lines are required to be OPERABLE,two on each SG to ensure a design basis accident that renders one SG unavailable for heat removal (in combination with a coincident loss of offsite power and a single active component failure) would not prevent control room operators from remotely opening an ADVon the unaffected SG. Failure to meet the LCOcan result in an inability to cool the affected unit to SDCSystem entry conditions when the SBCS is unavailable.

An ADV is considered OPERABLE when it is capable of providing a controlled relief of the main steam flow, and is capable of fully opening and closing on demand.

I APPLICABILITY In MODES1, 2, and 3, and in MODE4, when a SG is being relied upon for heat removal, the ADVs are required to be OPERABLE.

In MODES5 and 6, there is insufficient heat available to produce steam that could be released through the ADVs, and design basis accidents such as main steam line breaks, feedwater line breaks, and SGTRsare not credible events.

(continued)

PALOVERDEUNITS 1,2,3 B 3.7.4-4 REVISION58

BASES ACTIONS A. 1 The condition for this ACTIONis modified by a Note that states separate Condition entry is allowed for each SG.

This is acceptable because only one SG is required for RCS heat removal after a design basis accident, and because this Condition provides the appropriate Required Action and Completion Time for one inoperable ADV line on each SG.

With one ADV line on a SG inoperable, action must be taken to restore that ADV line to OPERABLE status within 7 days to meet the LCOfor each SG that has entered this Condition. The 7-day Completion Time takes into consideration the redundant capability afforded by the remaining OPERABLE ADV lines, the safety grade MSSVs,and the non-safety grade backup of the SBCS.

B.1 With two or more ADV lines inoperable with both ADV lines inoperable on one or more SGs, action must be taken to restore one ADV line on each SG to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Completion Time is reasonable to repair inoperable ADV lines, based on the availability of the Steam Bypass Control System and MSSVs, and the low probability of an event occurring during this period that requires the ADV I i nes.

NOTE:

Entry into Condition B for all four ADV lines simultaneously inoperable is not intended for voluntary removal of redundant systems or components from service in lieu of other alternatives that would not result in redundant systems or components being inoperable.

(continued)

PALOVERDEUNITS 1,2,3 B 3.7.4-5 REVISION58

ADVs B 3.7.4 BASES ACTIONS C.1 and C.2 (continued)

If the ADV lines cannot be restored to OPERABLE status within the associated Completion Time, the unit must be placed in a MODEin which the LCOdoes not apply. To achieve this status, the unit must be placed in at least MODE3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in MODE4, without reliance on I the SG for heat removal, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.

SURVEILLANCE SR 3.7.4.1 REQUIREMENTS To perform a controlled cooldown of the RCS, the ADVsmust be able to be opened and throttled through their full range.

This SR ensures the ADVs are tested through a full control cycle. Performance of inservice testing or use of an ADV during a unit cooldown may satisfy this requirement. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

REFERENCES 1. UFSAR,Section 10.3.

(continued)

PALOVERDEUNITS 1,2,3 B 3.7.4-6 REVISION58

SDCand Coolant Circulation - Low Water Level B 3.9.5 B 3.9 REFUELINGOPERATIONS B 3,9.5 Shutdown Cooling (SDC) and Coolant Circulation - Low Water Level BASES BACKGROUND The purposes of the SDCSystem in MODE6 are to remove decay heat and sensible heat from the Reactor Coolant System (RCS), as required by GDC34, to provide mixing of borated coolant, to provide sufficient coolant circulation to minimize the effects of a boron dilution accident, and to prevent boron stratification (Ref. 1). Heat is removed from the RCSby circulating reactor coolant through the SDCheat exchanger(s), where the heat is transferred to the Essential Cooling Water System via the SDCheat exchanger(s). The coolant is then returned to the RCSvia the RCScold leg(s).

Operation of the SDCSystem for normal cooldown or decay heat removal is manually accomplished from the control room.

The heat removal rate is adjusted by controlling the flow of reactor coolant through the SDCheat exchanger(s) and bypassing the heat exchanger(s). Mixing of the reactor coolant is maintained by this continuous circulation of reactor coolant through the SDCSystem, APPLICABLE If the reactor coolant temperature is not maintained below SAFETYANALYSES 200°F, boiling of the reactor coolant could result. This could lead to inadequate cooling of the reactor fuel due to the resulting loss of coolant in the reactor vessel.

Additionally, boiling of the reactor coolant could lead to a reduction in boron concentration in the coolant due to the boron plating out on components near the areas of the boiling activity, and because of the possible addition of water to the reactor vessel with a lower boron concentration than is required to keep the reactor subcritical. The loss of reactor coolant and the reduction of boron concentration in the reactor coolant would eventually challenge the integrity of the fuel cladding, which is a fission product barrier. Two trains of the SDCSystem are required to be OPERABLE,and one train is required to be in operation in MODE6, with the water level < 23 ft above the top of the reactor vessel flange, to prevent this challenge.

SDCand Coolant Circulation - Low Water Level satisfies Criterion 2 of 10 CFR50.36 (c)(2)(ii).

(continued)

PALOVERDEUNITS 1,2,3 B 3.9.5-I REVISION0

SDCand Coolant Circulation - LowWater Level B 3.9.5 BASES LCO In MODE6, with the water level < 23 ft above the top of the reactor vessel flange, both SDCloops must be OPERABLE.

Additionally, one loop of the SDCSystem must be in operation in order to provide:

a. Removal of decay heat;

b. Mixing of borated coolant to minimize the possibility of a criticality; and

c. Indication of reactor coolant temperature.

An OPERABLE SDCtrain is composedof an OPERABLE SDCpump (LPSI or CS) capable of providing flow to the SDCheat exchanger for heat removal. SDCpumps are OPERABLE if they are capable of being powered and are able to provide flow, if required. Note that the CS pumps shall not be used for normal operations if the water level is at or below the top of the hot-leg pipe (103' 1") due to concerns of potential air entrainment and gas binding of the CS pump (Ref. 2).

Both SDCpumpsmay be aligned to the Refueling Water Tank (RWT) to support filling the refueling cavity or for performance of required testing.

The LCO is modified by a Note that allows a required operating SDCloop to be removed from service for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> in each 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period, provided no operations are permitted that would cause a reduction of the RCSboron concentration. Boron concentration reduction is prohibited because uniform concentration distribution cannot be ensured without forced circulation. This permits operations such as core mapping or alterations in the vicinity of the reaGtor vessel hot leg nozzles, surveillance testing of ECCSpumps, and RCSto SDC isolation valve testing. During this 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period, decay heat is removed by natural convection to the large mass of water in the refueling cavity.

This LCOis modified by a Note that allows one SDCloop to be inoperable for a period of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> provided the other loop is OPERABLE and in operation. Prior to declaring the loop inoperable, consideration should be given to the existing plant configuration. This consideration should include that the core time to boil is not short, there is no draining operation to further reduce RCSwater level and that the capacity exists to inject borated water into the reactor vessel. This permits surveillance tests to be performed on the non-operating loop during a time when these tests are safe and possible.

(continued)

PALOVERDE UNITS1,2,3 B 3.9.5-2 REVISION58

SDCand Coolant Circulation - Low Water Level B 3.9.5 BASES APPLICABILITY Two SDCloops are required to be OPERABLE,and one SDCloop must be in operation in MODE6, with the water level < 23 ft above the top of the reactor vessel flange, to provide decay heat removal. Requirements for the SDCSystem in other MODESare covered by LCOs in Section 3.4, Reactor Coolant System. MODE6 requirements, with a water level _ 23 ft above the reactor vessel flange, are covered in LCO3.9.4, "Shutdown Cooling and Coolant Circulation - High Water Level."

ACTIONS A.1 and A.2 If one SDCloop is inoperable, action shall be immediately initiated and continued until the SDCloop is restored to OPERABLE status and to operation, or until _>23 ft of water level is established above the reactor vessel flange. When the water level is established at > 23 ft above the reactor vessel flange, the Applicability will change to that of LCO3.9.4, "Shutdown Cooling and Coolant Circulation - High Water Level ," and only one SDCloop is required to be OPERABLE and in operation. An immediate Completion Time is necessary for an operator to initiate corrective actions.

B.1 If no SDCloop is in operation or no SDCloops are OPERABLE, there will uniform establish be no forced boron circulation concentrations.to provide Reducedmixing boron to I concentrations can occur by the addition of water with lower boron concentration than that contained in the RCS.

Therefore, actions that reduce boron concentration shall be suspended immediately.

B.2 If no SDCloop is in operation or no SDCloops are OPERABLE, action shall be initiated immediately and continued without interruption to restore one SDCloop to OPERABLE status and operation. Since the unit is in Conditions A and B concurrently, the restoration of two OPERABLE SDCloops and one operating SDCloop should be accomplished expeditiously.

B.3 If no SDCloop is in operation or no SDCloops are OPERABLE, all containment penetrations providing direct access from (continued)

PALOVERDEUNITS 1,2,3 B 3.9.5-3 REVISION58

SDCand Coolant Circulation - LowWater Level B 3.9.5 BASES ACTIONS B.3 (Continued) the containment atmosphere to the outside atmosphere must be closed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. With the SDCloop requirements not met, the potential exists for the coolant to boil and release radioactive gas to the containment atmosphere.

Closing containment penetrations that are open to the outside atmosphere ensures that dose limits are not exceeded.

The Completion Time of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is reasonable, based on the low probability of the coolant boiling in that time.

SURVEILLANCE SR 3.9.5.1 REQUIREMENTS This Survei I Iance demonstrates that one SDCloop i s operating and circulating reactor coolant at a flowrate of greater than or equal to 3780 gpm. The flow rate is determined by the flow rate necessary to provide sufficient decay heat removal capability and to prevent thermal and boron stratification in the core. In addition, this Surveillance demonstrates that the other SDCloop is OPERABLE.

In addition, during operation of the SDCloop with the water level in the vicinity of the reactor vessel nozzles, the SDC loop flow rate determination must also consider the SDCpump suction requirements. The Surveillance Frequency is control led under the Surveillance Frequency Control Program.

SR 3.9.5.2 Verification that the required pump that is not in operation is OPERABLE ensures that an additional SDCpump can be placed in operation, if needed, to maintain decay heat removal and reactor coolant circulation. Verification is performed by verifying proper breaker alignment and power available to the required pump. The Surveillance Frequency i s control led under the Survei I Iance Frequency Control Program.

REFERENCES 1. UFSAR,Section 5.4.7.

2. PVNGS Calculation 13-MC-SI-0250,Appendix C.

PALOVERDEUNITS 1,2,3 B 3.9.5-4 REVISION58