ML17300B265

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Proposed Tech Specs,Changing Section 1.10 & 3.2.8 & Associated Bases for Obtaining Thyroid Dcfs Used in Definition of Dose Equivalent I-131
ML17300B265
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
Issue date: 06/17/1996
From:
ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:
Shared Package
ML17300B264 List:
References
NUDOCS 9606270244
Download: ML17300B265 (17)
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Text

G. MARKED-UP TECHNICAL SPECIFICATION PAGES UNIT 1 UNIT 2 UNIT 3 1-3 1-3 1-3 3/4 2-10 3/4 2-10 3/4 2-10 B 3/4 2-4 B 3/4 2-4 B 3/4 2-4 Page 9 of 9 9bOb270244 9bObi7 PDR ADOCK 05000528 P PDR

DEFINITIONS CORE OPERATING LIMITS REPORT 1.9a The CORE OPERATING LIMITS REPORT is the unit-specific document that provides core operating limits for the current operating reload cycle. These cycle-specific core operating limits shall be determined for each reload cycle in accordance with Technical Specification 6. 9. I. Plant operation within these operating limits is addressed in individual specifications.

DOSE E UIVALENT I-13l 1.10 DOSE E(UIVALENT I-131 shall be that concentration of I-131 (microcuries/

gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134 and I-135 actually present.

The thyroid dose conversion factors used for this calculation shall be those listed in Z "

II AVERAGE DISINTEGRATION ENERGY ~, I ICRP-30, Supplcmcnt to Part 1, pat',c 192-212, Table titled, Committed Dose Equivalcntin Tart cto~nsor Tissues r Intake of Unit Activity,'.

11 Z shall be the. average (weighted in proportion to the concentration of each radionuclide in the reactor coolant at, the time of sampling) of the sum of the average beta and gamma energies per disintegration (in MeV) for isotopes, other than iodines, with half-lives greater than 15 minutes, making up at least 95K of the total noniodine activity in the coolant.

ENGINEERED SAFETY FEATURES RESPONSE TIME

1. 12 The ENGINEERED SAFETY FEATURES RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i. eN s the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays where applicable.

FRBNNNNEYT NNNTATIFN

1. 13 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table l. l.

GASEOUS RADWASTE SYSTEM

1. 14 A GASEOUS RADWASTE SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

1.15 IDENTIFIED LEAKAGE shall be:

'. Leakage into closed systems, other than reactor coolant pump controlled bleed-off flow, such as pump seal or valve packing leaks that are captured and conducted to a sump or collecting tank, or

b. Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE, or
c. Reactor Coolant System leakage through a steam generator to the secondary system.

PALO VERDE - UNIT 1 1-3 AMENDMENT NO. 69

POMER DISTRIBUTIO 3/4.2.8 PRESSURIZER PRESSURE LIMITING CONDITION FOR OPERATION 2l30

~

3.2.8 2RRS The psia.

pressurizer pressure shall APPLICABILITY: HODES 1 and 2.

be maintained between ~5 psia and ACTION:

Mith the pressurizer pressure outside its above limits, restore the pressure to within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 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 />.

SURYEILLANCE RE UIREMENTS 4.2.8 The pressurizer pressure shall be determined to be within its limit at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

PALO VERDE " UNIT 1 3/4 2" 10 AMEI(OMENT NO. EF 39

POWER DISTRIBUTION LIMITS BASES-3/4.2.5 RCS FLOW RATE This specification is provided to ensure that the actual RCS total flow rate is maintained at or above the minimum value used in the safety analyses.

The minimum value used in the safety analyses is 95K of the design flow rate (164.0 x 10 ibm/hr) or 155.8 x 10 ibm/hr. The actual RCS flow rate is deter-mined by direct measurement and an uncertainty associated with that measurement is considered when comparing actual RCS flow rate to the minimum required value of 155.8 x 10 ibm/hr.

3/4.2.6 REACTOR COOLANT COLD LEG TEMPERATURE This specification is provided to ensure that the actual value of reactor coolant cold leg temperature is maintained within the range of values used in the safety analyses.,

3/4. 2.7 AXIAL.SHAPE INDEX This specification is provided to ensure that the actual value of the core average AXIAL SHAPE INDEX is maintained within the range of values used in the safety analyses.

3/4.2.8 PRESSURIZER PRESSURE This specification is provided to ensure that the actual value of safet anal ses. lhe va ueS ~

pressurizer pressure is maintained within the ran e of values used in the r prmsorlpel" p~5sQIQ QQg Me,

~~i~a~d vatues and ir'elude c,ors<dep~+c~ ~r,g+g~Q up~>gQq PALO VERDE - UNIT 1 B 3/4 2-4 AMENDMENT NO. 24

ll' II L, I

DEFINITIONS CORE OPERATING LIMITS REPORT 1.9a The CORE OPERATING LIMITS REPORT is the unit-specific document that provides core operating limits for the current operating reload cycle. These cycle-specific core operating limits shall be determined for each reload cycle in accordance with Technical Specification 6.9. 1. Plant operation within these operating limits is addressed in individual specifications.

DOSE E UIVALENT I-131 1.10 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries/

gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134 and I-135 actually present.

The thyroid dose conversion factors used for this calculation shall be those listed in II Table ICRP.30, Supplement to Part 1, page 192-212, Z " AVERAGE DISINTEGRATION ENERGY titled, "Committed Dose Equivalent in Target Owns or issu r Intake ol Unit Activity,"

l. 11 Z shall be the average (weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gamma energies per disintegration (in MeV) for isotopes, other than iodines, with half-lives greater than 15 minutes, making up at least 95K of the total noniodine activity in the coolant.

ENGINEERED SAFETY FEATURES RESPONSE TIME

1. 12 The ENGINEERED SAFETY FEATURES RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i. e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays where applicable.

FEEIE E Y ETATE 1.13 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1. 1.

GASEOUS RADMASTE SYSTEM

1. 14 A GASEOUS RADMASTE SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

IDENTIFIED LEAKAGE 1.15 IDENTIFIED LEAKAGE shall be:

a. Leakage into closed systems, other than reactor coolant pump controlled bleed-off flow, such as pump seal or valve packing leaks that are captured and conducted to a sump or collecting tank, or
b. Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE, or
c. Reactor Coolant'System leakage through a steam generator to the secondary system.

PALO VERDE - UNIT 2 1-3 AMENDMENT NO. 55

t r

POWER DISTRIBUTION LIMITS 3/4.2.8 PRESSURIZER PRESSURE LINJ'II~NG C 'DITION FOR OPERATION

~3.2.8 2295 The psia.

APPLICABILITY:

pressurizer pressure shall MODES 1 and 2*.

be maintained ZI9o between~peia and ACTION:

With the pressurizer pressure outside its above limits, restore the pressure to within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 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 />.

SURVEILLANCE RE UIREMENTS 4.2.8 The pressurizer pressure shall be determined to be within its limit at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

"See SpecialTest Exception 3.10.5 PALO VERDE " UNIT 2 3/4 2-10 AMENDMENT NO. 39, 55

I

~ ~

POMER DISTRIBUTION LIMITS BASES 3/4.2.5 RCS FLOM RATE This specification is provided to ensure that the actual RCS total flow rate minedd is maintained at or above the minimum value used in the safety analyses.

The minimum value used in the safety analyses is 95K of the design flow rate (164.0 x 10 ibm/hr) or 155.8 x 10 ibm/hr. The actual RCS flow rate is deter-by direct measurement and an uncertainty associated with that measurement is considered when comparing actual RCS flow rate to the minimum required value of 155.8 x 10'bm/hr.

3/4. 2. 6 REACTOR COOLANT COI 0 LEG TEMPERATURE This specification is provided to ensure that the actual value of reactor coolant cold leg temperature is maintained within the range of values used in the safety analyses.

3/4. 2.7 AXIAL SHAPE INDEX This specification is provided to ensure that the actual value of the core average AXIAL SHAPE INDEX is maintained within the range of values used in the safety analyses.

3/4.2.8 PRESSURIZER PRESSURE This specification is provided to ensure that the actual value of pressurizer pressure is maintained within the ran e of values used in the safety analyses.

hard.ic~ Values add values Qr ~

~nc.Iud'aid~$

~wsunpal- re~a'e LCD em M jn9f~Mf ~c~~~g~

PALO VERDE - UNIT 2 B 3/4 2-4 AMENDMENT NO. >9

N Pg 1

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ll I e

I

DEFINITIONS CORE OPERATING LIMITS REPORT 1.9a The CORE OPERATING LIHITS REPORT is the unit-specific document that provides core operating limits for the current operating reload cycle. These cycle-specific core operating limits shall be determined for each reload cycle in accordance with Technical Specification 6.9.1. Plant operation within these operating limits is addressed in individual specifications.

DOSE E UIVALENT I-131 1.10 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries/

gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134 and I-135 actually present.

The thyroid dose conversion factors used for this calculation shall be those listed in r 192-212, Table ICRP.30, Supplement to Part 1, page titled,'CommittcdDoseDIuivalcntinTargctorgansor "GE oISINTEGRATION ENERGY ~

Tissues r Intake of Unit Activity,

1. 11 E shall be the average (weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gamma energies per disintegration (in HeV) for isotopes, other than iodines, with half-lives greater than 15 minutes, making up at least 95K of the total noniodine activity in the coolant.

ENGINEERED SAFETY FEATURES RESPONSE TIHE

1. 12 The ENGINEERED SAFETY FEATURES RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF actuation setpoint at the channel sensor unti 1 the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays where applicable.

FREIRUE Y DTATtOII 1.13 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1.

GASEOUS RADWASTE SYSTEM

1. 14 A GASEOUS RADWASTE SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

IDENTIFIED LEAKAGE 1.15 IDENTIFIED LEAKAGE shall be:

a. Leakage into closed systems, other than reactor coolant pump controlled bleed-off flow, such as pump seal or valve packing leaks that are captured and conducted to a sump or collecting tank, or
b. Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE, or
c. Reactor Coolant System leakage through a steam generator to the secondary system.

PALO VERDE - UilIT 3 1" 3 AMENDMENT NO 42

~.

1(

I 100 ~4

0

' I POMER DISTRIBUTION LIMITS 3/4.2.8 PRESSURIZER PRESSURE

~LI ~ING CPIOITION FOR OPERATION 2l90

~

3.2.8 22/5 The psia.

pressurizer pressure shall be maintained between~ psia and APPLICABILITY: MODES 1 and 2.

ACTION:

I Mith the pressurizer pressure outside its above limits, restore the pressure to within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 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 />.

SURVEILLANCE RE UIREMENTS 4.2.8 The pressurizer pressure shall be determined to be within its limit at least once per l2 hours.

PALO VERDE - UNIT 3 3/4 2" 10 'MENOMENT NO. E7; <E

v POWER DISTRIBUTION HITS BASES 3/4.2.5 RCS FLOW RATE This specification is provided to ensure that the actual RCS total flow rate is maintained at or above the minimum value used in the safety analyses.

The minimum value used in the safety analysis is 95K of the design flow rate (164.0 x 10 ibm/hr} or 155.8 x IQS ibm/hr. The actual RCS flow rate is determined by direct measurement and an uncertainty associat'ed with that measurement is considered when comparing actual RCS flow rate to the minimum required value of 155.8 x 1Q ibm/hr.

3/4.2.6 REACTOR COOLANT COLO LEG TEMPERATURE

\

This specification is provided to ensure that the actual value of reactor coolant cold leg temperature is maintained within the'ange of values used in the safety analyses.

3/4.2.7 AXIAL SHAPE INDEX This specification is provided to ensure that the actual value of the core average AXIAL SHAPE INDEX is maintained within the range of values used in the safety analyses.

3/4.2.8 PRESSURIZER PRESSURE This specification is provided to ensure that the actual value of pressurizer pressure is maintain d within t safety analyses ~ vows ger' p~saor)~~~re-ecL mlues end tnc~ude; eoosidenthon yf v used in LCOeue-Ins~mp~ un~r4in4eg PALO VERDE - UNIT 3 B 3/4 2-4 AMEHDMEHT NO. 18

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