ML030090575

Issuance of Amendment 184 Letdown Line Break Dose Consequences Revision - TS Pages for Waterford Unit 3

ML030090575
Person / Time
Site:	Waterford
Issue date:	01/08/2003
From:	Kalyanam N NRC/NRR/DLPM/LPD4
To:	Entergy Operations
References
TAC MB3231
Download: ML030090575 (5)

Text

INDEX LIST OF FIGURES FIGURE PAGE 3.1-1 REQUIRED STORED BORIC ACID VOLUME AS A FUNCTION OF CO NCENTRATIO N............................................................................ 3/4 1-13 3.4-1 D ELETED .......................................................................................... 3/4 4-27 3.4-2 REACTOR COOLANT SYSTEM PRESSURE/TEMPERATURE LIMITATIONS FOR 0-8 EFFECTIVE FULL POWER YEARS (H EATU P) ........................................................................................... 3/4 4-30 3.4-3 REACTOR COOLANT SYSTEM PRESSURE/TEMPERATURE LIMITATIONS FOR 0-8 EFFECTIVE FULL POWER YEARS (CO O LDOW N)................................................................................... 3/4 4-31 4.7-1 SAMPLING PLAN FOR SNUBBER FUNCTIONAL TEST .................. 3/4 7-26 5.1-1 EXCLUSIO N AREA ............................................................................. 5-2 5.1-2 LOW POPULATION ZONE ................................................................. 5-3 5.1-3 SITE BOUNDARY FOR RADIOACTIVE GASEOUS AND LIQ UID EFFLUENTS ............................................................................ 5-4 6.2-1 OFFSITE ORGANIZATION FOR MANAGEMENT AND TECHNICAL SUPPORT ........................................................................ 6-3 6.2-2 PLANT OPERATIONS ORGANIZATION ............................................... 6-4 WATERFORD - UNIT 3 XIX AMENDMENT NO. 13,' 27,v.2 184

INDEX LIST OF TABLES (Continued)

TABLE PAGE 3.3-9 REMOTE SHUTDOWN INSTRUMENTATION .................................. 3/4 3-42 4.3-6 REMOTE SHUTDOWN INSTRUMENTATION SURVEILLANCE REQUIREMENTS .................................................. 3/4 3-43 3.3-10 ACCIDENT MONITORING INSTRUMENTATION .............................. 3/4 3-45 4.3-7 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ................................................... 3/4 3-46 3.3-12 D ELETED ........................................................................................... 3/4 3-56 4.3-8 D ELETED ........................................................................................... 3/4 3-58 3.3-13 EXPLOSIVE GAS MONITORING INSTRUMENTATION ................................................... 3/4 3-61 4.3-9 EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ................. 3/4 3-65 4.4-1 MINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED DURING INSERVICE INSPECTION ..................................................... 3/4 4-15 4.4-2 STEAM GENERATOR TUBE INSPECTION ........................................ 3/4 4-16 3.4-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES.. 3/4 4-20 3.4-2 REACTOR COOLANT SYSTEM CHEMISTRY ..................................... 3/4 4-22 4.4-3 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS SURVEILLANCE REQUIREMENTS ....................................................... 3/4 4-23 4.4-4 PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRA M................................................................... 3/4 4-25 WATERFORD - UNIT 3 XXI AMENDMENT NO. 9,,68,75,06,1 184

REACTOR COOLANT SYSTEM 314.4.7 SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.7 The specific activity of the primary coolant shall be limited to:

a. Less than or equal to 1.0 microcurie/gram DOSE EQUIVALENT 1-131, and

b. Less than or equal to 1 00/P microcuries/gram.

APPLICABILITY: MODES 1, 2, 3, 4, and 5.

ACTION:

MODES 1, 2, and 3*:

a. With the specific activity of the primary coolant greater than 1.0 microcurie/gram DOSE EQUIVALENT 1-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or exceeding 60 microcuries/gram DOSE EQUIVALENT 1-131, be in at least HOT STANDBY with Tavg less than 500°F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b. With-the specific activity of the primary coolant greater than 10Ol/E microcuries/gram, be in at least HOT STANDBY with Tavg less than 500°F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

MODES 1, 2, 3,4, and 5:

c. With the specific activity of the primary coolant greater than 1.0 microcurie/gram DOSE EQUIVALENT 1-131 or greater than 100/E microcuries/gram, perform the sampling and analysis requirements of item 4 a) of Table 4.4-4 until the specific activity of the primary coolant is restored to within its limits.

SURVEILLANCE REQUIREMENTS 4.4.7 The specific activity of the primary coolant shall be determined to be within the limits by performance of the sampling and analysis program of Table 4.4-4.

• With Tavg greater than or equal to 500 0F.

WATERFORD - UNIT 3 3/4 4-24 AMENDMENT NO. 6 184

TABLE 4.4-4 m PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM 0 MODES IN WHICH SAMPLE TYPE OF MEASUREMENT SAMPLE AND ANALYSIS AND ANALYSIS FREQUENCY AND ANALYSIS REQUIRED C

z

-I

1. Gross Activity Determination At least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 1,2,3,4

2. Isotopic Analysis for DOSE 1 per 14 days EQUIVALENT 1-131 Concentration 1

3. Radiochemical for R Determination 1 per 6 months*

4. Isotopic Analysis for Iodine a) Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, 1#,2#,3#,4#,5#

Including 1-131, 1-133, and 1-135 whenever the specific activity exceeds 1.0 pCi/gram, DOSE IN)

EQUIVALENT 1-131 cii1' or 100/2 pCi/gram, and b) One sample between 1,2,3 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following a THERMAL POWER change exceeding 15 % of the RATED THERMAL POWER within a 1-hour period.

m z0

• Sample to be taken after a minimum of 2 EFPD and 20 days of POWER OPERATION have elapsed since reactor m was last subcritical for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or longer.

z

-H z # Until the specific activity of the primary coolant system is restored within its limits.

0 4ýb

Pages 3/4 4-26 and 3/4 4-27 have been deleted. I WATERFORD - UNIT 3 3/4 4-26 AMENDMENT NO. 184 Next Page is 3/4 4-28