ST-HL-AE-4066, Proposed TS SR 4.6.1.1 Re Primary Containment Integrity & LCO 3.6.1.3 Re Operability of Containment Air Locks

Proposed TS SR 4.6.1.1 Re Primary Containment Integrity & LCO 3.6.1.3 Re Operability of Containment Air Locks

ML20114A420
Person / Time
Site:	South Texas
Issue date:	08/04/1992
From:	HOUSTON LIGHTING & POWER CO.
To:
Shared Package
ML20114A413	List: ML20114A411 ST-HL-AE-4066, Proposed TS SR 4.6.1.1 Re Primary Containment Integrity & LCO 3.6.1.3 Re Operability of Containment Air Locks
References
ST-HL-AE-4066, NUDOCS 9208110243
Download: ML20114A420 (10)

Text

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ATTACHMENT 3 ST HL-AE-t/o 6 6 PAGE l 0F _/0 -- .

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i APPENDIX B

( ) i MARKED-UP TECIINICAL SPECIFICATION PAGES E

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l 9208110243 920804 PDR P ADOCK 05000499 PDR

1 ATTACHMENT 3 3/4. 6 CONTAINMENT' SYSTEMS ST HL-AE-40M PAGE A 0F 10 '

7) 3/4.6.3 PRIMRY CONTAINMENT CONTAINMENT INTEGRITY LIMIT]NG CONDFff 0N FOR OoERATION .

3.6.1.1 .-

Primary CONTAINMENT INTEGRITY shall be maintained. '

APPLICABILITY: MODE 5 2, 2, 3 and 4.

ACTIONi .

I hour or be in at least HOT STANDBY within the next 6 h SHUTDOWN within the following3 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />.

gfRVEf ttANCE 9{QUIPEMENTS ,

4.6.1.1

- Primary CONTA!.NMENT INTEGRITY shall be demonstrated:

a.

At least once per 31 days by verifying that all penetrations" r.ot .

capable of being closed by OPERABLE containment automatic isoittion valvesby closed and required valves, blindto be closed during accident conditions are flanges

} or deactivated automatic valves secured in their positions, exce,pt as provided in Specification .:. a.3; b.

By verifying that each containment air lock is in compliance with the requirements of Specification 3.6.1.3; and c.

! a After each closing of each penetration subject to Type B testir.g . <-

l test,' by leak rate testing the seal with gas at a pressure i

than for theP,, 3@'QQ.and verifying that when the measured leakage rate

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, Speciff ation 4.6.1.2d for all other Type B and C penetrat the cor

ined leakage rate is less than 0.60 L,. .

(445 Psid .

r "Except valves, blind flanges, and deactivated automatic in the closed position.

each often thanCOLDonce per SHUTDOWN 92 days. except that such verification need not b

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CONTA1WENT SYSTEMS

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CONTAI RENT LEAKAGE j PAGE.3__'10M i

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numMC CONDMON FDR OPERATTON :

p t 3.5.1.2 Containment leakabe rates shall be 11mitad to:,-

l a. -

An overall integrated leakage rate of less than or equal ,, 0.30K by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P, sig.-

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A. combined leakage rete of less than 0.60fL for all-penetrations and valves subject to Type,3 and C tests, M pressur'ized to P,.

j - APPLICABILITY: E DES 1, 2, 3 and 4.

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[ . With eithe* the measured overall. integrated containment leakage rate exceeding 4

0.75 L, or the esasured_ combined leakage rate for all penetrations and valves -

subject to Types 5 and.C tests exceed 1ng 0.60 L , restore the overall inte : _

grated leakage rate to less than 0.75 L, and_ the cortined leakage rata for all creasing the Reactor Coolant System tamparature above 200*F.penet j;

SURVFTttANCF REDUfRFMFWTE P

. 4.6.1.2 The containment _ leakage rates shall- be demonstrated

, and provisions specified or_ endorsed in Appendix J of _20 CFR Part 50: -

a.

i Three Type A tests (Overall-Integrated " Containment' Leakage' Rate) shall be conducted at 40 2 2D_mnth intervals during shutdown at

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a pressure not less than P,', T& during each 10 year __ service period. The third test of ,

f shutdown for the 10 year ch set shall be~ conducted during the ant inservice inspection;: *

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SOUTH TEXAS - UNITS 1 & 2 -3/4 6-2

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Unit 1 - Amendment No. 26 )

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Unit 2 - Amendment No.16 ' l I

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ATTACHMENT 3 CONTAINMENT SYSTEMS ST HL AE 406 6 PAGE 3 0F A -

SURVEILL ANCE REOUIREMEhTS (Centinuad) b.

If my periodic Type A test fails to meet 0.75 L,, the test schedule for subsequent Type A tests shall be reviewed and approved b" the' Commissien. If two consecutive Type A tests fail to meet 0.15 L ,

a Type A test shall be perfonned at least every 18 months until two '

consecutive Type A tests meet 0.75 L, at which time the above test schedule ray be resumed;

c. The accuracy of each Type A test shall be verified by a' supplemental test which: .

1) ' Confirms the accuracy of the test by verifying that the supple-mental equation:test result, Lc, is in hccordance with the following. , . j, lLc $ ,, 4 ,)I S,0.25 L, where L, is the measured Type-A test leakage and L, is the superimposed leak;

-- 2) Has a duration sufficient to establish accurately the change in leakage rate between the Type A test and the supplemental test;

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3) Requires that the rate at which gas is injected into the contain-

- ment or bled from the containment during the supplement,.? test is between 0.75 L,and 1.25 L,.

d. Type B and C teste chall be conducted with gas at a pressure not -

less than P,,@ Q pli at intervals no greater than 24 months

, except for tests involving:

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1) Air locks, '

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2) Purge supply and exhaust isolation valves with resilient material '

seals, and '

, 3) Penetrations using continuous Leakage Monitoring Systems.

e. Air locks shall be tested and demonstrated OPERhBLE by the require-ments of Specification 4.6.1.3;

f. Purge shply and exhaust isolation valves with resilient material seals shall be testeo and demonstrated OPERABLE by the requirements o,f Specification 4.6.1.7.2 or 4.6.1.7.3, as applicable; SOUTH TEXA5 - UNITS 1 & 2 3/4 6-3 Unit 1 - Amendment No. 4

,;0h"AllMENT SYSTEMS ATTACHMENT 3 1 ST HL AE.t/o 4 4,-

PAGE 3 ,

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Stm.EfttANCE RE0lf1REMENTS (Continued)

g. __

System may be excluded, subject to the provision Section III.C.3, when determining the combined leakage rate prov;id g the Seal System and valves are pressurized to at least 1.10 P QV364pfD and the seal system capacity is adequate to maintain

. system pressure for at least 30 days; -

h.

Type B tests ing Systen forconducted shall be penetrations at P employina = rantinuous Leakage Monito greater than once per 3 years; and,, /$ M at intervals no 1.

The provisions of Specification 4.1.2 are not applicable. .

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50m TEXA5 - UNITS 1 & 2 3/4 6-4

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i COWAINHENT SYSTEMS

_COWAINMENT AIR LOCKS

.10 1 11MITING CONDITION FOR OPERATION '

3.6.1.3 Each containment air lock shall be OPERA 8L5 with:

a.

Soth doors closed except when the air lock is being used for normal -

e transit entry and exit through the containment, then at least one air lock door shall be closed, and -

b. .

n overall air lock leakane rate of less than or equal- to 0.05 L, at a'bI g D40 5 PSET)

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

ACTIDW:- '

a.

With one containment air lock door inoperable:

1.

'restore Maintain at least the OPERABLE air lock door closed and ei the inoperable air lock door to OPERABLE status within -

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or lock the OPERABLE air lock door closed;

, ' 2.

a . Operation may then continue until performance of the next required overall ajr lock leakage test provided that the OPERABLE I ) airdays; 31 lock door is verified to be locked closed

• at least once per

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Otherwise, 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 />; and 4.

The provisions of Specification 3.0.4'are not applicable.

• b.

With the containment air lock inoperable, except as the result of an . . .

inoperable air lock door, maintain at least one air. lock door' closed;l - .

restore the inoperable air lock to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> *- .

or be in at least SHUTDOWN within HOT STANDBY the following within 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. 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 ,

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ATTACHMENT 3 ST-HL-AE. tot le CONTAINMENT SYSTEM 5

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1 SURVEftt MCE REOUIREMENTS

4. 6.1. 3 t Each containment air lock shall be demonstrated OPERABLE:

a.

Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following each closing, except when the air lock is being used for multiple entries, then at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> by verifying seal leakage is less than 0.01 L, as determined by prec,ision~

flow measurements when measured for at least 30 second< with the volume between the reals at a cane (ant ~ pressure (trf476-NSERT b. QJo'r Le.ss ruw Th ; , , m. -

b By conducting overali air lock leakage f.ests at not less than P,,

. (9 5 34- MON and verifying the overell air lock leakage ra it o i it:

d 1) At least once per 6 months,* and '

2) Prior to establishing CONTAINMENT INTEGRITY when maintenance

- has been performed on the air lock that could affect the air.

lock sealing capability.**

c.

! At least once per 6 months by verifying that only one door in each 1 air lock can be opened at a time.

l s d.

l By ve'rifying at least once per 7 days that the instrument air pres-

.sure in the header to the personnel airlock seals is 3,90 psig.

e.

By verifying the door seal pneumatic system OPERABLE at least once per 18 months by conducting a seal pneu:natic system leak test and verifying that system pressure does not decay more than 1.5 psi from 90 psig minimurn within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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• The provisions of Specification 4.0.2 are not applicable.

• • This represents an exemption to Appendix J, paragraph III.D 2 of 10 CFR Part 50.

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i j 3/4.6 CONTAINMENT SYSTEMS ATTACHMENT 3 i

ST HL-AE PAGE  ? te(c,(,

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/0 L BASFS 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY 1-

. Primary CONTAINMENT INTECRITY ensures that the release of radioactive ~

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i materials from the containment atmosphere will be restricted to those leakage -

paths and associated leak rates assumed in the safety analyses. This j

restriction, in conjunction with the leakage rate limitation, will limit i

the SITE BOUNDARY radiation doses to within the dose guideline values of 10 CFR Part 100 during. accident conditions.

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3/4.6.1.2 CONTAINMr 8.EAKAGE sM MO.6 T56 i

The limitati, :entainment leak e rates ensureLthat'the total

! containment leakage ,,

me will not exces l analyses at the pean accident pressure, Pphe value

,. As an added assumed in the safety conservatism, the i

j measured overall integrated leakage rate-is further limited to less than or equal to 0.75_ L, during performance of the periodic test to account for possible-j degradation of the containment' leakage barriers between leakage tests.

j The surveillance testing for m4asuring leakage rates is consistent with

, the requirements of Appendix J of 10 CFR Part 50.

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j 3/4.6.1.3 -CONTAINMENT AIR LOCKS-i The limitations on closure and leak rate for the containment air locks l

are required to meet the restrictions on CONTAINMENT INTEGRITY and containment leak rate. Surveillance testing of the air lock seals provides assurance that 4 the overall air lock leakage will not become excessive due to seal damage -

during the intervals between air. lock leakage tests.

3/4.6.1.4 INTERNAL PRESSURE The limitations on containment internal pressure ensure that: (1) the containment structure is prevented from exceeding its design negative pressure-

-p differential with respect to the outside atmosphere of 3.5 psig, and (2) the containment peak pressure does not exceed the design pressure of 56.5 psig l

during LOCA or steam line break conditions.

1 i The maximum peak nra"ure expected to be obtained from a-LOCA or steam t line break event is(57%$\p)T1 .The limit of 0.3 psig- nitial positive containment pressure wn : Fu4t the' total pressure t psig, which is less than design pressure and is ccpsistent with the saf lyses..

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NT3 ST HL AE qog

^7 CONTAINMENT SYSTEMS l BASES 3/4.6.1.5 AIR TEMPERATURE The limitations on containment average air temperature ensure that the over-all containment average air temperature does not exceed the initial temperature condition assumed in the safety analysis for a LOCA or steam line break ~

accident. Measurements shall be made by fixed instruments, prior to determin-ing the average air temperature, y _

3/4. 6.1. 6 CONTAINMENT STRUC1VRAL INTEGRITY  % 5 P316 (P This limitation e'nsures that the ructural integrity of the containment will be maintained comparable to the ori nal design standards for the life of the facility. Structural integrit a stred to ensure that the containment will with-stand the maximum pressure of $ i) in the event of a LOCA or steam line break accident. The measurement of cUn ainment tendon lift-off force, the tensile tests of the tendon wires, the visual examination of tendons, anchorages and exposed interior and exterior surfaces of the containment, and the Type A leakage test are sufficient to demonstrate this capability.

The Surveillance Requirements for demonstrating the containment's structural integrity are in compliance with the recommendations of Regulatory Guide 1.35,

" Inservice Inspection of Ungrouted Tendons in Prestressed Concrete Containment i

' Structures," and proposed Regulatory Guide 1.35.1, " Determining Prestressing Forces for inspection of Prestressed Concrete Containments," April 1979.

i The required Special Reports from ary engineering evaluation of containment abnormalities shall include a description of the tendon condition, the condition of the concrete (especially at tendon anchorages), the inspection procedures, the tolerances on cracking, the results of the engineering evaluation, and the correc-tive actions taken.

3/4.6.1.7 CONTAINMENT VENTILATION SYSTEM The 48-inch containment purge supply and exhaust isolation valves are required to be sealed closed during plant operations since these valves have not been demonstrated capable of closing during a LOCA or steam line break accident.

Maintaining these valves sealed closed during plant operation ensures that exces-sive quantities of radioactive materials will not be released via the Containment Purge System. To provide assurance that these containment valves cannot be inad-vertently opened, the valves are sealed closed in accordance with Standard Review Plan 6.2.4 which includes mechanical devices to seal or lock the valve closed, or prevents power from being supplied to the valve operator.

The use of the containment purge lines is restricted to the 18-inch purge supply and exhaust isolation valves since, unlike the 48-inch valves, the 18-inch valves are capable of closing during a LOCA or steam line break accident. There-SOUTH TEXAS - UNITS 1 & 2 0 3/4 6-2 -

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ATTACHMENT 3 m

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5.0 DESIGN FEATURES A 5.1 SITE EXCLUSION AREA 5.1.1 The Exclusion Area shall be as shown in Figure 5.1-1.

LOW POPULATION ZONE

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5.1. 2 The Low Population Zone shall be as shown in Figure 5.1-2.  ;

MAP DEFINING UNRESTRICTED AREAS AND ' SITE BOUNDARY FOR RADI0 ACTIVE GASEOUS AhD-LIQUID EFFLUENTS 5.1. 3 Information regarding radioactive gaseous and liquid effluents, which 4

will allow identification of structures and release points as well as defini-i

' tion of UNRESTRICTED AREAS within the SITE BOUNDARY;that are Leessible to MEMBERS OF THE PUBLIC, shall be as shown in Figures 5.1-3 and 5.1-4.

The definition of UNRESTRICTED AREA used in impless tin j fications has been expanded over that in 10 CFR 20.3(a)g (17).these Technical Spect-The UNRESTRICTED

' AREA boundary may coincide tith the Exclusion (fenced) Area boundary, as defined in 10 CFR 100.3(a), but the UNRESTRICTED AREA does not include areas over water bodies. The concept of UNRESTRICTED AREAS, established at ot beyond the SITE BOUNDARY, is utilized in the Limiting Conditions for Operation to keep' levels of radioactive materials in liquid and gaseous effluents as low as is reason-ably achievable, pursuant to 10 CFR 50.36a.

5.2 -CONTAINMENT a

! C0HFIGURATION 5.2.1 The r actor containment building is a steel-lined, reinforced concrete buildir of cylindrical shape, with a dome roof and having the following design -

a features.

a. -Nominal inside diameter = 150 feet.

b. Nominal inside height = 241.25 feet,

c. Minimum thickness of concrete walls = 4 feet.

. d. Minimum thickness of concrete roof = 3 feet.

e.

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Minimum thickness of. concrete floor mat = 18 feet.

f. Nominal thickness of steel liner = 3/8 inches. -

' g. Net free volume =NfW165/cu6tc/fd DESIGN PRESSURE AND TEMPERATURE 9 XlO6 - 3 41 XIO#M 5.2.2 The reactor containment building is designed and shall be maintained for a maximum internal' pressure of 56.5 psig and a temperature of 286*F.

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