ML20236N451

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Proposed Tech Specs,Revising Allowable Containment Pressure Range Based on Reanalysis of Limiting Main Steam Line Break Peak Containment Pressure Event
ML20236N451
Person / Time
Site: Waterford Entergy icon.png
Issue date: 11/05/1987
From:
LOUISIANA POWER & LIGHT CO.
To:
Shared Package
ML20236N266 List:
References
NUDOCS 8711160171
Download: ML20236N451 (11)


Text

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.e INDEX LIST OF FIGURES FIGURE PAGE 3.1-0 SHUTOOWN MARGIN AS A FUNCTION 0F COLD LEG TEMPERATURE............................

3/4 1-3a 3.1-1 REQUIRED STORED BORIC ACID VOLUME AS A FUNCTION OF CONCENTRATION.......................................

3/4 1-13 i

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 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_2-2 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 LINIT BASED ON CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEACs OPERABLE)..

3/4 2-8 3.2-3 DNSR 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 /TE ^ ATURE LIMITATIONS FOR 0-8 EFFECTIVE FULL MER 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

.C 1 00xTAl m.cxT.1 0 = V: Tc= =AT =...............

3/4 : 12 l

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 20NE................................

S-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'0 ORGANIZATION......................

6-4 WATERFORD - UNIT 3 XIX AMENOMENT NO. 13 9711160171 871105 PDR ADOCK 05000382

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' CONTAINMENT SYSTEMS-l INTERNAL PRESSURE i

LIMITING CONDITION FOR OPERATION 3.6.1.4 Primary containment internal pressure shall be maintained withi. th:

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. C 1.. LE SS YtIA H 20 INCHES H 0 GAUG E.AHO i

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G l? E' A T E R T*H A N I4,375 pris, 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 />.

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SURVEILLANCE REQUIREMENTS d

4.6.1.4 The primary containment internal pressure shall be determined to be I

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 />.

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CONTAINMENT SYSTEMS BASES i

. 3/4.6.1.4 INTERNAL PRESSURE-k

. The limitations on containment internal pressure ensure that (1) the Of -

containment structure. is prevented from exceeding its. design negative pressure' W

- differential with respect to the annulus atmosphere o.f;0.65 psid, (2) the

'D containment peak pressure does not exceed the design pressure of 44,psig

=i 2'

' during either.-LOCA or steam line ' break conditions, and (3) the mini' mum pressure cof the ECCS performance analysis (BTP CSB 6-1).is satisfied.'

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. peak pre

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~eam li ibrea is 43 psig.

e limits Figure

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.niti positi cont ent pre re and perature l'limi heftot press e to 1

's tha 44 ps which i ess.than e desi ressur and is onsist wit e

saf y analys The-limit of:14.375 psia for initial negative containment pressure ensures

-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 I

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 CONTAINMENT VESSEL STRUCTURAL INTEGRITY

.This limitation ensures. that the structural 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 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 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> 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 BOUNDARY 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 the purge line for systems to be used during plant operation.

WATERFORD - UNIT 3 B 3/4 6-2

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INSERT 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 inches water (approximately 0.72 psig) will limit the total pressure to less than 44 psig which is less than the design pressure and is consistent with the safety analyses.

The limit for initial positive containment pressure includes a correction of 1.20 inches water for possible instrument error and an additional 0.94 inches water for conservatism.

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INDEX LIST OF FIGURES-FIGURE PAGE l

'3.1-0 SHUT 00WN MARGIN AS A FUNCTION j

.OF COLD LEG TEMPERATURE............................

3/4 1-3a-l 1

3.1 -

REQUIRED STORED BORIC ACID VOLUME AS A' FUNCTION OF

]

CONCENTRATION.......................................

3/4 1-13 g:

.3.1-1A-REQUIRED. POWER REDUCTION AFTER SINGLE CEA DEVIATION 3/4 1-20a-3.1-2 CEA INSERTION LIMITS VS THERMAL POWER...........l..

3/4 1 3.1-3 PART LENGTH CEA INSERTION LIMIT VS THERMAL POWER....

3/4 1-28a 1

3.2-1 ALLOWABLE PEAK LINEAR HEAT RATE VS Tc..............

, 3/4 2-2 j

3.2-1A

. ALLOWABLE PEAK LINEAR HEAT RATE VS Tc FOR COLSS OUT 0F. SERVICE.........................................

3/4 2-2A-3.2-2 DNBR-MARGIN OPERATING LIMIT BASED ON CORE PROTECTION q

CALCULATORS.(COLSS OUT OF SERVICE, CEACs OPERABLE)..

3/4 2-8 1

3.2-3 DNBR MARGIN OPERATING LIMIT BASED ON CORE PROTECTION CALCULATORS'(COLSS OUT OF SERVICE,CEACS INOPERA8LE).........................................

3/4 2-9

3. 4-1.

DOSE EQUIVALENT I-131 PRIMARY COOLANT SPECIFIC ACTIVITY LIMIT VERSUS fERCENT 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 (NEATUP)...........................................

3/4 4-30 3.4-3 REACTOR C0CLANT SYSTEM PRESSURE / TEMPERATURE LIMITATIONS FOR 0-8 EFFECTIVE FULL POWER YEARS (C00LDOWN).........................................

3/4 4-31 1

l 3.0 1 CONTAI.%'"CXT PRESCOC V: TC"PCRATCC...............

3/4 0 12 l-j 4.7-1 SAMPLING PLAN FOR SNU8BER FUNCTIONAL TEST..........

3/4 7-26 5.1-1 EXCLUSION AREA.....................................

5-2 5.1-2 LOW POPULATION 20NE................................

5-3 5.1-3 SITE BOUNDARY FOR RADI0 ACTIVE GASEOUS AND LIQUID EFFLUENTS....................................

5-4 6.2-1 0FFSITE ORGANIZATION FOR MANAGEMENT AND 1ECNNICAL SUPP0RT.................................

6-3 6.2-2

. PLANT OPERATIONS ORGANIZATION......................

6-4 WATERFORD - UNIT 3 XIX AMEN 0 MENT No. 13 i

____-____-___--_-_._____m

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i CONTAINMENT SYSTEMS INTERNAL PRESSURE LIMITING CONDITION FOR OPERATION 3,6.1.4 Primary containment internal. pressure shall be' maintained withir, th:

i 1.; u vi F ;,-. :.; 1.- L E SS THA N 2 7 INCHE S. Hg G GA UG E.A N O G R C A T E R TH A N 14, 3 75 p ria,,,

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 SHUTOOWN 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 />.

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WATERFORD - UNIT 3 3/4 6-12 1

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, CONTAINMENT SYSTEMS i

BASES 3/4;6.1.4 INTERNAL PRESSURE L

The limitations on containment internal pressure ensure that (1) the k

containment structure is prevented from exceeding its design negative pressure E.

differential with respect to the annulus atmosphere of 0.65 psid, (2) the M-containment peak pressure does not exceed the design pressure of 44,psig

' 3 during either LOCA or steam line break conditions, and (3) the miniinum pressure of.the ECCS performance analysis (BTP CSB 6-1) is satisfied.

f e maxim peak pre

're'expec d to be

~tained om a

~eam 11 'brea e

t is 43 psig.

e limits Figure

.6-1 fo niti positi cont -

ment pre re and perature 1 limi he tot - press e to 1

's tha 44 ps which i ess than e desi ressur and is onsist wit e

saf y analys The limit of 14.375 psia for initial negative containment pressure ensures 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 i

containment peak air temperature does not exceed the design temperature of

~

269.3'F during LOCA conditions and 413.B'F during MSLB conditions and is consistent'with the safety analyses.

3/4.6.1.6 CONTAINMENT VESSEL STRUCTURAL INTEGRITY i

This limitation ensures.that the structural integrity of t,he containment j

steel vessel will be maintained comparable'to the original design standards for the life of the facility.

Structural integrity is required to ensure that j

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.

I 3/4.6.1.7 CONTAINMENT VENTILATION SYSTEM The' use of the containment purge valves is restricted to 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> 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 E

July 1, 1975.

The purge valves-have been modified to limit the opening to I

approximately 52' to ensure the valves will close during a LOCA or MSLB;

}

and therefore, the SITE BOUNDARY doses are maintained within the guidelines l

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 WATERFORD - UNIT 3 8 3/4 6-2 l

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/.o M SL6 The maximum peak pressure e::pected to be obtained from.a teek event is:

J2.3 the psig. The limit: for it.itial positive contaitunent pressure of +90-+27 inches water (approximately/Orff psig) will limit the total pressure to less than 44 psig which is less than the design pressure and is-consistent with the' safety analyses.

The limit'for initial' positive containment pressure includes a-correction.offl.20 inches water for possible' instrument error and'an additional 6-9& inches water'for conservatism.

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