ML20236H212
| ML20236H212 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 07/29/1987 |
| From: | LOUISIANA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20236H204 | List: |
| References | |
| NUDOCS 8708050100 | |
| Download: ML20236H212 (13) | |
Text
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l NPF-38-62 ATTACHMENT A 8708050100 870729 PDR ADDCK 05000382-P PDR
INDEX LIST OF FIGURES FIGURE PAGE 3.1-0 SHUTOOWN MARGIN AS A FUNCTION OF COLD LEG TEMPERATURE............................ 3/4 1-3a 3.1-1 REQUIRED STORED BORIC ACID VOLUME AS A FUNCTION OF CONCEN1 RATION...................................... 3/4 1-13 3.1-1A REQUIRED POWER REDUCTION AFTER SINGLE CEA DEVIATION 3/4 1-20a' 3.1-2 CEA INSERTION LIMITS VS THERMAL P0WER.............. 3/4 1-27 3.1-3 PART LENGTH CEA INSERTION LIMIT VS THERMAL POWER... 3/4 1-28a 3.2-1 ALLOWABLE PEAK LINEAR HEAT RATE VS Tc.............. 3/4 2 ;
3.2-1A ALLOWABLE PEAK LINEAR HEAT RATE VS Tc FOR COLSS OUT OF SERVICE.........................................
3/4 2-2A 3.2-2 DNBR MARGIN OPERATING LIMIT BASED ON CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEACs OPERABLE).. 3/4 2-8 3.2-3 DNBR MARGIN OPERATING LIMIT BASED ON CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE,CEACS IN0PERABLE)......................................... 3/4 2-9 3.4-1 DOSE EQUIVALENT I-131 PRIMARY COOLANT SPECIFIC ACTIVITY LIMIT VERSUS PERCENT OF RATED THERMAL POWER WITH THE PRIMARY COOLANT SPECIFIC ACTIVITY >1.0 pCi/ GRAM DOSE EQUIVALENT I-131....... 3/4 4-27 3.4-2 REACTOR COOLANT SYSTEM PRESSURE / TEMPERATURE LIMITATIONS FOR 0-8 EFFECTIVE FULL POWER YEARS (HEATUP)........................................... 3/4 4-30 3.4-3 REACTOR COOLANT SYSTEM PRESSURE / TEMPERATURE LIMITATIONS FOR 0-8 EFFECTIVE FULL POWER YEARS (C00LDOWN)......................................... 3/4 4-31 3.6-1 CONTAINMENT PRESSURE VS TEMPERATURE ............... 3/4 6-12 4.7-1 SAMPLING PLAN FOR SNUBBER FUNCTIONAL TEST.......... 3/4 7-26 5.1-1 EXCLUSION AREA..................................... 5-2 5.1-2 LOW POPULATION Z0NE................................ 5-3 5.1-3 SITE BOUNDARY FOR RADI0 ACTIVE GASEOUS AND LIQUID EFFLUENTS................................... 5-4 6.2-1 0FFSITE ORGANIZATION FOR MANAGEMENT AND TECHNICAL SUPP0RT................................. 6-3 6.2-2 .
PLANT OPERATIONS ORGANIZATION...................... .
6-4 WATERFORD - UNIT 3 XIX AMEN 0 MENT NO. 13 1.
CONTAINMENT SYSTEMS INTERNAL PRESSURE I LIMITING CONDITION FOR OPERATION i
3.6.1.4 Primary containment internal pressure shall be maintained within the limits of Figure 3.6-1.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
With the containment internal pressure outside of the limits above, restore the internal pressure to within the limits within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-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 /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.1.4 The primary containment internal pressure shall be determined to be within the limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
WATERFORD - UNIT 3 3/4 6-11
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' l CONTAINMENT SYSTEMS BASES l
3/4.6.1.4 TNTERNAL PRESSU_RE l i The limitations on containment internal pressure ensure that (1) the ! containment structure is prevented from exceeding its design negative pressure ! differential with respect to the annulus atmosphere of 0.65 psid, (2) the containment peak pressure does not exceed the design pressure of 44,psig during either LOCA or steam line break conditions, and (3) the mini'um m pressure of the ECCS performance analysis (BTP CSB 6-1) is satisfied. j The maximum peak pressure expected to be obtained from a steam line break event is 43.76 psig. The limits of Figure 3.6-1 for initial positive contain-ment pressure and temperature will limit the total pressure to less than ; 44 psig which is less than the design pressure and is consistent with the j safety analyses. i The limit of 14.375 psia for initial negative containment pressure ensures that the minimum containment pressure is cansistent with the ECCS performance l analysis ensuring core reflood under LOCA conditions. 3/4.6.1.5 AIR TEMPERATURE The limitation on containment average air temperature ensures that the containment peak air temperature does not exceed the design temperature of 269.3 F during LOCA conditions and 413.5*F during MSLB conditions and is consistent with the safety analyses. 3/4.6.1.6 CONTAlNtiENT VESSEL STRUCTURAL INTEGRITY , l This limitat ?m ensures that the structural integrity of the containment i steel vessel will be maintained comparable to the original design standards j for the life of the facility. Structural integrity is required to ensure that i the vessel will withstand the maximum pressure of 43.76 psig in the event of I a main steam line break accident. A visual inspection in conjunction with Type A leakage test is sufficient to demonstrate this capability. . 3/4.6.1.7 CONTAINMENT VENTILATION SYSTEM The use of the containment purge valves is restricted to 90 hours per year in accordance with Standard Review Plan 6.2.4 for plants with the Safety Evaluation Report for the Construction License issued prior to July 1, 1975. The purge valves have been modified to limit the opening to approximately 52 to ensure the valves will close during a LOCA or MSLB; and therefore, the SITE B0UNDARY doses are maintained within the guidelines of 10 CFR Part 100. The purge valves, as modified, comply with all provisions of BTP CSB 6-4 except for the recommended size of th; purge line for systems to be used during plant operation. WATERFORD - UNIT 3 8 3/4 6-2
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I i t i NPF-38-62 ATTACHMENT B i i
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INDEX LIST OF FIGURES i i FIGURE PAGE 3.1-0 SHUTDOWN MARGIN AS A FUNCTION OF COLD LEG TEMPERATURE............................ 3/4 1-3a 3.1-1 REQUIRED STORED BORIC ACID VOLUME AS A FUNCTION OF CONCENTRATION...................................... 3/4 1-13 3.1-1A REQUIRED POWER REDUCTION AFTER SINGLE CEA DEVIATION 3/4 1-20a-3.1-2 CEA INSERTION LIMITS VS THERMAL P0WER...........'... 3/4 1-27 i 3.1-3 PART LENGTH CEA INSERTION LIMIT VS THERMAL POWER... 3/4 1-28a j 3.2-1 ALLOWABLE PEAK LINEAR HEAT RATE VS Tc.............. , 3/4 2-2 l 3.2-1A ALLOWABLE PEAK LINEAR HEAT RATE VS Tc FOR COLSS OUT OF SERVICE......................................... 3/4 2-2A 3.2-2 DNBR MARGIN OPERATING LIMIT BASED ON CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEACs OPERABLE).. 3/4 2-8 3.2-3 DNBR MARGIN OPERATING LIMIT BASED ON CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE,CEACS IN0PERABLE)......................................... 3/4 2-9 1 3.4-1 DOSE EQUIVALENT I-131 PRIMARY COOLANT SPECIFIC
' ACTIVITY LIMIT VERSUS PERCENT OF RATED THERMAL POWER WITH THE PRIMARY COOLANT SPECIFIC ACTIVITY >1.0 pCi/ GRAM DOSE EQUIVALENT I-131. . . . . . . ' 3/4 4-27 3.4-2 REACTOR COOLANT SYSTEM PRESSURE / TEMPERATURE LIMITATIONS FOR 0-8 EFFECTIVE FULL POWER YEARS j (HEATUP)........................................... 3/4 4-30 1 3.4-3 G CTOR COOLANT SYSTEM PRESSURE / TEMPERATURE LIMITATIONS FOR 0-8 EFFECTIVE FULL POWER YEARS *
(C00LDOWN)......................................... 3/4 4-31 0.C 1 CONTAINMENT PRESSunt V: TEMrtnATURt . . . . . . . . . . . . . . . :/4 ; 12 l 4.7-1 SAMPLING PLAN FOR SNUBBER FUNCTIONAL TEST. . . . . . . . . . 3/4 7-26 S.1-1 AREA..................................... EXCLUSION 5-2 S.1-2 LOW POPULATION 20NE................................ 5-3 S.1-3 SITE BOUNDARY FOR RADI0 ACTIVE GASEOUS AND LIQUID EFFLUENTS................................... 5-4 6.2-1 0FFSITE ORGANIZATION FOR MANAGEMENT AND TECHNICAL SUPP0RT................................. 6-3 6.2-2 . PLANT OPERATIONS ORGANIZATION...................... . 6-4 l WATERFORD - UNIT 3 XIX AMEN 0 MENT NO. 13 l l
l CONTAINMENT SYSTEMS INTERNAL PRESSURE i LIMITING CONDITION FOR OPERATION , l 3.6.1.4 Primary containment internal pressure shall be maintained withir. th; l iim;La vi F ;uu. . 3.C 1. l.E SS THA N 20 INCHES Hz O GA UG E . A tJ O , Gl? C A T C R THRIA I 4 , 3 7 5 p s-ta, , MODES 1, 2, 3, and 4. APPLICABILITY: ACTION: With the containment internal pressure outside of the limits above, restore the internal pressure to within the limits within 1 hour or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. i l SURVEILLANCE REQUIREMENTS i l
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4.6.1.4 The primary containment internal pressure shall be determined to be l within the limits at least once per 12 hours. 1 t WATERFORD - UNIT 3 3/4 6-11
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i CONTAINMENT SYSTEMS l BASES 3/4.6.1.4 INTERNAL PRESSURE l L The limitations on containment internal pressure ensure that (1) the k containment structure is prevented from exceeding its design negative pressure , W differential with respect to the annulus atmosphere of 0.65 psid, (2) the l M containment peak pressure does not exceed the design pressure of 44,psig 3 during either LOCA or steam line break conditions, and (3) t.he mini' mum pressure of the ECCS performance analysis (BTP CSB 6-1) is satisfied. i h'e maxim peak pre sQre expe)c ed to be obtained ' rom a -team li 'brea ey/nt is 43 psig. e limits f' Figure .6-1 fo niti positi cont * - l ment pre re and t perature 1 limi he tot press e to 1 's than 44 ps which i ess than e desi ressurf and is onsist with e ; saf y analyse . / l The limit of 14.375 psia for initial negative containment pressure ensures l that the minimum containment pressure is consistent with the ECCS performance analysis ensuring core reflood under LOCA conditions. 3/4.6.1.5 AIR TEMPERATURE The limitation on containment average air temperature ensures that the containment peak air temperature does not exceed the design temperature of 2M.3 F during LOCA conditions and 413.5 F during MSLB conditions and is i consistent with the safety analyses. i l 3/4.6.1.6 CONTAINMENT VESSEL STRUCTURAL IMIF.GRITY This limitation ensures that the structral integrity of the containment steel vessel will be maintained comparable to the original design standards for the life of the facility. Structural integrity is required to ensure that the vessel will withstand the maximum pressure of 43.76 psig in the event of j a main steam line break accident. A visual inspection in conjunction with ; Type A leakage test is sufficient to demonstrate this capability. . l l 1 3/4.6.1.7 CONTAINMENT VENTILATION SYSTEM i l The use of the containment purge valves is restricted to 90 hours per year in accordance with Standard Review Plan 6.2.4 for plants with the Safety Evaluation Report for the Construction License issued prior to July 1, 1975. The purge valves have been modified to limit the opening to approximately 52 to ensure the valves will close during a LOCA or MSLB; j and therefore, the SITE BOUNDARY doses are maintained within the guidelines j of 10 CFR Part 100. The purge valves, as modified, comply with all provisions ! of BTP CSB 6-4 except for the recommended size of the purge line for systems j to be used during plant operation. i 4 WATERFORD - UNIT 3 B 3/4 6-2 ! l s
y l l l I INSERT l The maximum peak pressure expected to be obtained from a LOCA event is 43.2 psig. The limit for initial positive containment pressure of +20 l inches water (approximately 0.72 psig) will limit the total pressure to i less than 44 psig which is less than the design pressure and is consistent with the safety , analyses. The limit for initial positive containment i pressure includes a correction of 1.20 inches water for possible instrument error and an additional 0.94 inches water for conservatism. I i i J l l 1
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NPF-38-62 ATTACHMENT C 1
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