ML18057A428

Proposed Tech Spec 4.5.1 Re Integrated Leakage Rate Tests

ML18057A428
Person / Time
Site:	Palisades
Issue date:	08/21/1990
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18057A425	List: ML18057A424 ML18057A427 ML18057A428
References
NUDOCS 9008310199
Download: ML18057A428 (12)

Text

4.5 e

CONTAINMENT TESTS Applicability

• Applies to containment leakage *and structural integrity.

Objective To verify that potential leakage from the containment and the pre-stressing tendon loads are maintained within specified values.

Specifications 4.5.1 Integrated Leakage Rate Tests A surveillance test program for the containment overall integrated I leakage rate shall meet the 10 CFR 50, Appendix J, Type A test /

requirements or approved exemptions. /

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I 9008310199 900821 PDR ADOCK 05000255

\. P PNU ,- 4-25 Amendment No TSP0790-0053-NL04

This Page Intentionally Blank 4-26 TSP0790-0053-NL04

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4.5.2 Loca-1 Leak -Detect-ion- Tes-ts

a. Te-st-(1) Local leak rate tests shall be performed at a pressure of not less than 55 psig.

(2) Local leak rate tests for checking air lock door seals within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of each door opening shall be performed at a pressure of not less than 10 psig.

(3) Acceptable methods of testing are halogen gas detection, soap bubble, pressure decay, or eauivalent.

(4) The local leak rate shall be measured for each of the following components:

(a) Containment penetrations that employ resilient seal gaskets, sealant compounds, or bellows.

(b) Air lock and eauipment door seals.

(c) Fuel transfer tube.

(d) Isolation valves on the testable fluid systems' lines penetrating the containment.

(e) Other containment components which reauire leak repair in order to meet the acceptance criterion for any integrated leak rate test.

b. Acceptance Crite-ria (1) The total leakage from all penetrations and isolation valves shall not exceed 0.60 La.

(2) The leakage for an air lock door seal test shall not exceed 0.023 La.

c. Co-r-rec-ti-ve- Act-ion (1) If at any time it is determined that 0.60 La is exceeded, repairs shall be initiated immediately.

4-27 Amendment No. ll, tl~.

TSP0790-0053~NL04

4.S CONTAINMENT TESTS (Cont'd)

Basis The containment is designed for an accident pressure of SS psig. (l)

While the reactor is operating, the internal environment of the containment will be air at approximately atmospheric pressure and a temperature of about 104°F. With these initial conditions, following a LOCA, the temperature of the steam-air mixture at the peak accident pressure of SS psig is 283°F.

Prior to initial operation, the containment was strength-tested at 63 psig and then leak rate tested. The design objective of this preoperational leak rate test was established as 0.1% by weight per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at SS psig. This leakage rate is consistent with the 2

construction of the containment, ( ) which is eauipped with independent leak-testable penetrations and contains channels over all unaccessible containment liner welds, which were independently leak-tested during construction.

Accident analyses have been performed on the basis of a leakage rate of 0.1% by weight per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. With this leakage rate and with a reactor power level of 2S30 MWt, the potential public exposure would be below 10 CFR 100 guideline values in the event of the Maximum

~ypothetical Accident. <3 )

The performance of a periodic integrated leak rate test during plant life provides a current assessment of potential leakage from the containment in case of an accident that would pressurize the interior of the containment. In order to provide a realistic appraisal of the integrity of the containment under accident conditions, this periodic leak rate test is to be performed without preliminary leak detection surveys or leak repairs and containment isolation valves are to be closed in the normal manner.

This normal manner is a coincident two-of-four high radiation or two-of-four high containment pressure signals which will close all containment isolation valves not reauired for engineered safety features except the component cooling lines' valves which are closed by CHP only. The control system is designed on a two-channel (right I and left) concept with redundancy and physical separation. Each channel (4) is capable of initiating containment isolation.

4-33 Amendment No. 109, TSP0790-00S3-NL04

4.5

• CONTAINMENT TESTS (Cont'd)

• The Type A test reauirements including pretest test methods, test I pressure, acceptance criteria, and reporting reauiteinents are in -/

accordance with 10 CFR 50, Appendix J, reauirements or approved I exemptions. I The freauency of the periodic integrated leak rate test is keyed to the refueling schedule for the reactor because these tests can best be performed during refueling shutdowns. The specified freauency is as specified in 10 CFR Part SO, Appendix J which is based on three major considerations. First is the low probability of leaks in the liner because of (a) the test of the leak tightness of the welds during erection; (b) conformance of the complete containment to a low leak rate at 55 psig during preoperational testing which in consistent with 0.1% leakage at design basis accident (DBA) conditions: and (c) absence of any significant stresses in the liner during reactor operation. Second is the more freauent testing, at the full accident pressure, of those portions of the containment envelope th.at are most likely to develop leaks during reactor operation (penetrations and isolation valves) and the low value (0.601 ) of the total leakage that is specified as acceptable from a

penetrations and isolation valves. Third is the tendon stress surveillance program which provides assurance that 4-34 Amendment No. tl, l~~.

TSP0790-0053-NL04

ATTACHMENT Consumers Power Company Palisades Plant Docket 50-255 MARKED UP TECHNICAL SPECIFICATION PAGES August 21, 1990 6 Pages TSP0790-0053-NL04

/U~*'fC ,.,IL ~ .. II -e~I. ~ /0 ~Fie 5"0, If,._ .. ~,.. f . 'ry/'~ A

~s~ ..-1""* ...... 1-, or a.r p,.o vor.d exemptions,

4. 5 COliT.A.DMEl'ilT ~TS Atmllsabllitz

~liH to coz:t*inm*:it leak&p azid structural. 1Ate¢t7.

ObJe~!ve To ver1!7 that pote=ti&l lealcage t'rcm the sontai:Mnt m4 the pre-stnss inc tcmdmi lo&d.I ue maiat&ined vithi:l specit1*ci values.

Soec1t1sat1oc.s Inugrsted. I.e!lwJe a&te Tests I:t*CZ"&ted. leak rate testa sa&U 'be pen'omed. prier to !.:Uti pl&At operatioc.s at cozttainment 4esip pl'ffsun (P&) o'! 55 1111 I :.6

& test prasure (? t) o'! &t leui: 26 psig to .est&Ol!s* ~

ec'tive =-auz-ed lea& rates, r.lll &Dd. Ltm. A \ l6 tap ~* ot 50°F vill be utili:ed.. !he ~

• st tem-(2)

.sure ~ vithou-: s:i7

. leak detectica ~ or leak rep&in ~lllSl;l*&tel3' p~cr to or d.uri:C the test, ept u acted. be.low.

(3) .M&Jcr leak r=it the integrated. leak nte teat, sh&ll. be &l leuage mea.si.:r-..:e.cts.

rep&i!', sh&!.l 'be

• tin&l integ:-&ted. le:lk :-ate sequent retest scl:l.edule.

(4) All systeu vtis.h, wider. ~sid.e:t .. oAdition.s, 'beccme an ex:e:-

siozi Qt t!le ccat-...~191"

cs'9here <iurinc i:i* g::'Sted. leak rate t ts. Closure ot co~:u1 n:ent isol&tion va.l.ves t:i ~e &es:pl!sneci ey e ~or.:&! :icde or (S) ~e terw sh.al: :ct be less th&z:l 24 ~ tea-:

le&S't -:vo :;i:"'!.or tens :;ir:>viie e Jbc~u test iun.tio:i.

suppl.ementar.r :ea::s, si:.c:i as ::iaaau:'"'..:g t!le ~**

?'9~uired. "!Q r.-:.~ to -::ie s-:ar:i:ig ~ci:it, er by !.=;cs .. a.

d.ac:tS-:ra.te v-al.iiiit7 ot  ::easur~ts.

....25

e e 4.5 Tl:ie o*J"!mnm &lloVacle leak&p n.te 1.mdu DB.A' c:onditioua, L sa&ll aot exceed O. !O veipt perce:t pe:- 24 a.curs.

(2) ~e &llovable opentioD&l leakqe rate, I.to' vbicl:l 1 u'\. prior to resim;tion ot pavv opvati=. tolloving

' uceri 0. 75Lt *.men Lt is defined by 4.5,i.b(J).

(3). ~ ~. lnbp nte, Lt, at the ndw:ed t wbich c:ue a HtUI to eed La (Lt:/I.am) W1leaa sb&ll

.

.

be eq,ua.l to La (Pt/Pa )~

r..tm./L UH ot the leakage UUUHd m'ing precperation&l

.. -eed.I 1

./' *

o. 7, u

\16 I

tests.

• The sul:ls ipta ~ and l reter to i I

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&ecident pressure d. :-educed presa\:Z'e I I

. Cor:o:ec:tive Acticm t:Jr Re't (l) a.cc:eptance c::!tL-ion, -:lie be ::-epeated p~d.ed local leakaee nte uuure=enta ~d. the lu&age n~e ilt:'er- ,,-.:..

ence I.chined bT repairs ::- th.* over~ ma~ i:tag:rated leu rate to a value ot the s.Uavable ope:-atioU&l.

leakage rate, r..tc *

(2) 'rhe reduc~!.on in le e et!'ec:ted by ~e  :-e=ia.!.r ot iselatioD V&l.ves leak rate test reaU:-:s.

ii. ?reg,uanc;;

6 (l.) Atte::- t!ie/i:Utia.l preO!)erstion&l le~  :-3.-:e tea-es). s. set

't)E' mm;el;r ~tia.l ~ter"tL.a d.UZ"'..:ig es.ch  ::~-year se_-ri::

sc*~, oe c:~~uc~e~

!..s !C:J.': <!.c:vn !or t!le l0-1ear  !.:se..-n.c~ I::

!.-:26 ~ ~. -~

4.5 CONTAINMENT TESTS (Contd)

If any periodic integrated leak rate test fails to m cceptance criteria, the test schedule app le to subsequ integrated leak rate tests wil e reviewed and approved he Commission.

e. Report of Test Results

_..---

Each integrated l~ate-------

'

test will tee al report which will include summa of ction tests and leak test of the recirculation 4.5.2 Local Leak Detection Tests

a. Test (1) Local leak rate tests shall be performed at a pressure of not less than 55 psig.

(2) Local leak rate tests for checking air lock door seals I within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of each door opening shall be performed I at a pressure of not less than 10 psig. I (3) Acceptable methods of testing are halogen gas detection, I soap bubble, pressure decay, or equivalent.

(4) The local leak rate shall be measured for each of the I following components:

(a) Containment penetrations that employ resilient seal gaskets, sealant compounds, or bellows.

(b) Air lock and equipment door seals.

(c) Fuel transfer tube.

(d) Isolation valves on the testable fluid systems.'

lines penetrating the containment.

(e) Other containment components which require leak repair in order to meet the acceptance criterion for any integrated leak rate test.

b. Acceptance Criteria (1) The total leakage from all penetrations and isolation I valves shall not exceed 0.60 La.

(2) The leakage for an air lock door seal test shall not I exceed 0.023 La. I

c. Corrective Action (1) If at any time it is determined that 0.60 La is exceeded, repairs shall be initiated immediately.

4-27 Amendment No. lt,~

June 1, 1989

4.5 CONTAINMENT TESTS (Continued) I 4.5.2 Local Leak Detection Tests (Continued) I If repairs are not completed and conformance to the acceptance criterion of 4.5.2.b(l) is not demonstrated I within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the Plant shall be placed in at least I hot shutdown 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 at least I 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 />. I (2) If at any time it is determined that total containment I leakage exceeds La, within one hour action shall be I initiated to bring the Plant to hot shutdown within the I next six (6) hours and cold shutdown within the following I thirty (30) hours. I (3) If air lock door seal leakage is greater than 0.023 La, I repairs shall be initiated immediately to restore the I door to less than specification 4.5.2.b(2). In the event I repairs cannot be completed within 7 days, the Plant I shall be brought to a hot shutdown condition within the I next six (6) hours and cold shutdown within the I following thirty (30) hours. I If air lock door seal leakage results in one (1) door I causing total containment leakage to exceed 0.60 La, the door shall be declared inoperable and the remaining operable door shall be immediately locked closed and I

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tested within four (4) hours. As long as *the remaining I door is found to be operable, the provisions of 4.5.2.c(2) I do not apply. Repairs shall be initiated immediately to I establish conformance with specification 4.5.2.b(l). In I the event conformance to this specification cannot be I established within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> the Plant shall be brought to I a hot shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and cold shutdown I within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. I

d. Test Frequency (1) Individual penetrations and containment isolation valves shall be leak rate tested at a frequency of at least every six months prior to the first postoperational integrated leak rate test and at a frequency of at least every refueling thereafter, not exceeding a tw~~year interval, except as specified in (a) and (b) below:

(a) The containment equipment hatch and the fuel transfer tube shall be tested at each refueling shutdown or after each time used, if that be sooner.

4-28 tMaftg' -e 1 Amendment No 1t, 126 June 1, 1989 TSP0489-0115-NL04

4.5 CONTAINMENT TESTS (Cont'd)

~

The containment is designed for an accident pressure of 55 psig. (l)

While the reactor is operating, the internal environment of the containment will be air at approximately atmospheric pressure and a temperature of about 104°F. With these initial conditions, following a LOCA, the temperature of the steam-air mixture at the peak accident pressure of 55 psig is 283°F.

Prior to initial operation, the containment was strength-tested at 63 psig and then leak rate tested. The design objective of this preoperational leak rate test was established as 0.1% by weight per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 55 psig. This leakage rate is consistent with the 2

construction of the containment,( ) which is equipped with independent leak-testable penetrations and contains channels over all unaccessible containment liner welds, which were independently leak-tested during construction.

Accident analyses have been performed on the basis of a leak.age rate of 0.1% by weight per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. With this leak.age rate and with a reactor power level of 2530 MWt, the potential public exposure would be below 10 CFR 100 guideline values in the event of the Maximum Hypothetical. Accident. C3 >

The performance of a periodic integrated leak rate test during plant life provides a current assessment of potential leak.age from the containment in case of an accident that would pressurize the interior of the containment. In order to provide a realistic appraisal of the integrity of the containment under accident conditions, this periodic leak rate test is to be performed without preliminary leak detection surveys or*leak repairs and containment isolation valves are to be closed in the normal manner.

This normal manner is a coincident two-of-four high radiation or two-of-four high containment pressure signals which will close all containment isolation valves not required for engineered safety features except the component cooling lines' valves which are closed

~~ The control system is designed on a two-channel (right and le~ concept with redundancy and physical separation. Each channel 4

is capable of initiating containment isolation. < >

4-33 Amendment No * .i>>,,

October 28, 1987 TSP0887-0139-NL04

...

!

4.5 CONTAINMENT TESTS (Cont'd) of 28 psig for the periodic integrated leak r s sufficiently high to provide an accurate measureme of and it duplicates the preoperational leak specification provides relationships conservative m er the measured leakage of air 28 psig to the potential le4kage a steam-air mixture at psig and 283°F. The specification also a ws for possible erioration of the leakage rate betwee~ tests by re . ring tha nly 75% of the allowable leakage rates actually be me The basis for these deterioration allowances is Part 50, Appendix J which is believed to be conserva e and e confirmed or denied by periodic testing. ndicated to be n the deterioration allowances will altered based The dur on of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for the integrated est shed to provide a minimum level of accuracy an to for ly cyclic variation in temperature and thermal radiat The frequency of the periodic integrated leak rate.test is keyed to I

I the refueling schedule for the reactor because these tests can best be performed during refueling shutdowns. The specified frequency _is as specified in 10 CFR Part 50, Appendix J which is based on three.*

major considerations. First is the low probability of leaks in the liner because of (a) the test of the leak tightness of the welds I during erection; (b) conformance of the complete containment to a low leak rate at 55 psig during preoperational testing which in consistent with 0.1% leakage at design basis accident (DBA) conditions: and (c) absence of any significant stresses in the liner during reactor operation. Second is the more frequent testing, at the full accident pressure, of those portions of the containment envelope that are most likely to develop leaks during reactor operation (penetrations and isolation valves) and the low value (0.60L ) of the total leakage that is specified as acceptable from a

penetrations and isolation valves. Third is the tendon stress surveillance program which provides assurance that

,,...~ f I.I ;,.I htl#f i. C ArP'"di1e J;'" r~ 'J" ,*,,..,""'I If+.

4-34 Amendment No. l'l, hS, Oeteher 28, 1987 TSP0887-0139-NL04