ML18106A214

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Proposed Tech Specs Pages,Revising TS to Adopt Option B to 10CFR50,App J,For Type B & C Testing & Modify Existing TS Wording for Previous Adoption of Option B on Type a Testing
ML18106A214
Person / Time
Site: Salem  PSEG icon.png
Issue date: 12/15/1997
From:
Public Service Enterprise Group
To:
Shared Package
ML18106A212 List:
References
NUDOCS 9712230222
Download: ML18106A214 (18)
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Text

'.' Documen.t Control Attachment 3

  • LR-N970663 LCR S97-27 SALEM GENERATING STATION Units 1 and 2 FACILITY OPERATING LICENSES DPR 70 and 75 DOCKET NOS. 50-272 and 50-311 REVISIONS TO THE TECHNICAL SPECIFICATIONS (TS)

TECHNICAL SPECIFICATION PAGES WITH PROPOSED CHANGES The following Technical Specifications for Facility Operating Licenses No. DPR-70 and 75 are affected by this change request:

Technical Specification Unit 1 3/4.6.1.2 3/4 6-2 3/4.6.1.3 3/4 6-5 3/4 6-5a 4.6.1.6.1 3/4 6-8 Section 6.8.4 6-19 Bases for 3/4.6.1 B 3/4 6-1 Bases for 3/4.6.1.6 B 3/4 6-2 Unit 2 4.6.1.1 3/4 6-1 3/4.6.1.2 3/4 6-2 3/4.6.1.3 3/4 6-4 3/4 6-5 4.6.1.6.1 3/4 6-8 Section 6.8.4 6-19 Bases for 3/4.6.1 B 3/4 6-1 Bases for 3/4.6.1.6 B 3/4 6-2 9712230222 971215 1 PDR ADOCK 05000272 I I

P PDR

~

CONTAINMENT SYSTEMS ~.v~~

~4~L~

CONTAINMENT LEAKAGE

~T~~w LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:

(r-yt°e..A ~).....,_____

a. An overall integrated leakage rateAef '5La, 0.10 percent ey *,;ei9ht'
  • 1::fte- c EH'l ta i nme Rt a i r f' e r 2 4 h-0 ti rs at fre.!:ri-gn----p1--e-s~ e , ( fl . O
psigl-*
b. A combined leakage rate ~f~ 0.60 Lal for all penetrations and valves subject to Type B and C tests.s wR.tlR f*Elssur:..zed to Pa.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With either (a) the measured overall integrated containment leakage rate (rrF-A ~) ~

-e-Kceeel:in§' 0.7§ La, or (b) with the measured combined leakage rate for all.

penetrations and valves subject to Types Band C tests ~beading Q,eO La,.c;-~~~~~

restore the leakage rate(s) to within the limit(s) prior to increasing the Reactor Coolant System temperature above 200°F.

SURVEILLANCE REQUIREMENTS

==================================================================

aA>

4.6.1.2 The containment leakage rates shall be demonstrated at tfie follows: ~

\

a. Type A tests shall be -~S.G-.-§.4-(-Gt-in ~

.Q-01.+for:maRse Hith .".ppeae!iJE J sf 10CFR §.Q..,-G~on B, using tl:oie

..rm.etl:iods and px:ouision" of Eeg,,htory Gujde 1.163, S-ep-t.~:r lril 0 $ as 1*j me di fi ea b-y-a-pp-r-evcl~'mf> ti on s

  • I *

/

b. Type B and C tests shall be conducted ~~-~

oe* o~ HlOCFR ~GJ'l*t-i-eR-A.,-wHl::i ~.a.s-a.45 aes.i.gl=l p-rni;su.ra ( 17, Q psi§) a~

IL!'

~ervaJ,s RS '§'Hi&tar tRaR 24 meRUi.s exsspt for tests in*.rolving air leek~; *

c. Air locks shall be tested and demonstrated OPERABLE in ooRvor::nar:i.ce t-uith .11zflJ30Rdi1t J of lOGFR §0, Option h, per sti:F.*cillanee Requirement 4.6.1.3';

SALEM - UNIT 1 3/4 6-2 Amendment No. 189

CONTAINMENT SYSTEMS CONTAINMENT AIR LOCKS LIMITING CONOITON FOR OPERATION 3.6.l.3 Each containment air lock shall be OPERABLE with:

a. Both doors closed except when the a1 r lock is being used for normal transit entry and exit through the containrrent, tnen at

..*'- least one air lock door shal 1 be closed. and APPLICABILITY: MODES l, 2, 3 and 4 ACTION:

With an a1r lock inoperable, restore the 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 HOT STAN08Y within th* next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLO 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 RE~IREMENTS I

SALEM - UNIT l 3/4 6-~ Amendment No. 89

CONTAINMENT SYSTEMS CONTAINMENT AIR LOCKS SURVEILLANCE REQJlREMENTS (Continued) 1.-"

c. At 1east*once tier 6 nonths by v*rify1ng that only one door in each air lock can be open1d at a t11111.

3/4 6-Si Amendment No. 89 SALEM - UHIT l

CONTAINMENT SYSTEMS CONTAINMENT STRUCTURAL INTEGRITY LIMITING CONDITIONS FOR OPERATION

===========================================================

3.6.1.6 The structural integrity of the containment shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.1.6.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With the structural integrity of the containment not conforming to the above requirements, restore the structural integrity to within the limits prior to increasing the Reactor Coolant ~ystem temperature above 200°F.

SURVEILLANCE REQUIREMENTS

===========================================================

4.6.1.6.1 Containment Surfaces The structural integrity of the exposed accessible interior and exterior surfaces of the containment, including the liner plate, shall be determined~ a visual inspection ef these suFfaccs~

l'his insp.ect...i.D-~ha.ll be perf.G.rned prior ...Ge-t.-he Type A cor;;itainm~i:it l9aka~e

-rate test (Feference Specification 4,5,1,2) to verify nG-a~ent ohanges :i:R

.a.pp.ear:a-nGe--or- 0.1;.fie.r a.&no.:emal deg-r.aQ.at~oH. If the '.l.'¥-FJe-A--te-s-t-i-s pierformed at J:Q yga:i;; int;Qr;Hal!; 1 t***o sdciitienal inspei;;tions sha 11 be per::fori:geH:l st*

a15151::ex.:.!'l'.ately eqtHi:l .;...-.~.:;:*;z.]..:; ;:!*...'"r-L-*.;i .:.1-.a-ed-owl'l:s 'eet*.:een Type A: Tcst:i.

4.6.1.6.2 Reports Any abnormal degradation of the containment structure detected during the above required inspections shall be evaluated for reportability pursuant to 10CFR50.72 and 10CFRS0.73. The evaluation shall be documented and shall include a description of the condition of the concrete, the inspection procedure, the tolerances on cracking, and the corrective action taken.

SALEM - UNIT 1 3/4 6-8 Amendment No. 184

ADMINISTRATIVE ~TRC

~==========================

(vi) A procedure identifying (a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective action.

d. Backup Method for Determining Subcooling Margin A program which will ensure the capability to accurately monitor the Reactor Coolant System Subcooling Margin. This program *hall include the following:

(i) Training of personnel, and (ii) Procedure* for monitoring

e. Postaccident Sampling A program* which will ensure the capability to obtain and analyze reactor coolant, radioactive iodine* and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions. Th* program *hall include the following:

(i) Training of personnel (ii) Procedure* for sampling and analy*i*,

(iii) Provi*ion* for maintenance of *amplinq and analysis equipment.

A.

  • It i* acceptable if the licensee maintain* details of th* program in plant operation manuals.

SALEM - UNIT l 6-19 Amendment No. 133

INSERT A 6.8.4.f Primary Containment Leakage Rate Testing Program A program shall be established, implemented, and maintained to comply with the leakage rate testing of the containment as required by 10CFR50.54(o) and 10CFR50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program", dated September 1995.

The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa, is 47.0 psig.

The maximum allowable containment leakage rate, La, at Pa, shall be 0.1% of primary containment air weight per day.

Leakage Rate Acceptance Criteria are:

a. Primary containment leakage rate acceptance criterion is less than or equal to 1.0 La. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are less than or equal to 0.6 La for Type B and Type C tests and less than or equal to 0.75 La for Type A tests;
b. Air lock testing acceptance criteria are:
1) Overall air lock leakage rate is less than or equal to 0. 05 La when tested at greater than or equal to Pa,
2) Seal leakage rate less than or equal to 0.01 La per hour when the gap between the door seals is pressurized to 10.0 psig.

Test frequencies and applicable extensions will be controlled by the Primary Containment Leakage Rate Testing Program.

The provisions of Specification 4.0.3 will be applied to the Primary Containment Leakage Rate Testing Program.

3/4.6 CONTAINMENT SYSTEMS BASES

==================================================================

3/4.6.i ?R:MARY CONTAINMENT 3/4.6.1.i CONTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the accident analyses. This restriction, in conjunction with the leakage rate limitation, will limit the site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions.

3/4.6.1.2 CONTAINMENT LEAKAGE The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the accident analyses at the~(accident pressure, Pa. As an added conservatism, the measured overall integrated leakage rateYis further limited to s 0.75 L~ or

< 0.75 L., as applicable, during perform~nc~of the periodic test to account for possible degradation of the containment leakage barriers between leakage tests. (iyr2.-ft -f~) ,

l<)..>

The surveillance testing for measuring leakage rates ~ consistent with tfic rcquircfficRt:s ef h~pel'leiix "J" ef 10 CFR §0\- fu Cvi~ L..~ ~

3/ 4. 6. 1. 3 CONTAINMENT AIR LOCKS T~~ lP~.

The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY andAcontainmefi"t iea*ki=r.a<E-e. Surveillance testing of the air lock seals provide assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.

SALEM - UNIT l B 3/4 6-1

CONTAINMENT SYSTEMS BASES

=====~============================================================

3/4.6.l.4 INTERNAL PRESSURE 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 outside atmosphere of 3.5 psig and 2) the containment peak pressure does not exceed the design pressure of 47 psig during the limiting pipe break condit~ons. The pipe breaks considered are LOCA and steam line breaks.

The limit of 0.3 psig for initial positive containment pressure is consistent with the accident analyses initial conditions.

The maximum p~ak pressure expected to be obtained from a LOCA or steam line break event is $ 47 psig.

3/4.6.l.5 AIR TEMPERATURE The limitations on containment average air temperature ensure that the overall containment average air temperature does not exceed the initial temperature condition assumed in the accident analysis for a LOCA or steam line break. In order to determine the containment average air temperature, an average is calculated using measurements taken at locations within containment selected to provide a representative sample of the overall containment atmosphere.

3/4.6.1.6 CONTAINMENT STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment will be maintained comparable to the original design standards for the life of the facility. Structural integrity is required to ensure that the containment will withstand the design pressure. The visual inspections of the concrete and liner and the Type A leakage test~re sufficient to demonstrate this capability. J

~tl~~~~~

~~*l~~

1~<9~

SALEM - UNIT 1 B 3/4 6-2 Amendment No. 195

" J.L4. 6 CONTAINMENT sYsAs 3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.

APPLICABILITY: MODES l, 2, 3 and 4.

ACTION:

Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour 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.l.l Primary CONTAINMENT IN!EGRITY shall be demonstrated:

a. At least once per 31 days by verifying that all penetrations* not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated.autanatic valves secured in their positions, except for valves that may be opened under Administrative control as permitted by Specification 3.6.3.l, and all equipment hatches are closed and sealed.
b. By verifying that each containment air lock is OPERABLE per Specification 3.6.l.3.
c. After each closing of a penetration subject to Type B testing, except containment air locks, if opened following a Type A or B test, by leak rate testing ti:be seaLwith .gae et Pa (47 paig) H\d --s:ll:'a.fy4.n~ ~it~t; *Jfies

--the mc~e~=ed-1--e--.:..~=g~ rate fo= ~heec eoale !s-useea ~e ~fi~ ~-~~

  • d~t:eZ'iit+/-n~d 15~ .......... i..
  • t ... :3p"'owl.f*.i.:-~.i.'ffi:' 4 . 6. i. 2 . d £01* a:-11 othe ... **Type-""~5,._.---

_,,,,,,._ "'i;=,-

w1u c pwii~ "'k-=-~' --- *-ch-'c-

..... a-t:.~-g~ ~- '-;.-,-A ottUJ ....r. ..... u"::"'"w~=s ,,.,....._e _:tis.-":l:"'~ll!i-"'

~r...J--e .. .._..,~t~. ,;_;,,, ~--- ....,""=~'iaq-e%:

!s,'1,., --

~qua co =

n - "'"3: ..

Cl-;-6*a- ha. . ~ ~ ~ ~ CMi~ J...~ ~

  • ~ cP~.* ..
  • Except vents, drains, test connections, etc. which are (l) one inch nominal pipe diameter or less, (2) located inside the containment, and (3) locked, sealed, or otherwise secured in the closed position. These penetrations shall be verified closed at least once per 92 days.

SALEM - UNIT 2 3/4 6-1 Amendment No. 1 72

CONTAINMENT SYSTEMS

\_.., I\

CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to~=:..-.~~~~~~~~~~~--

(Tf'2' A (A....lr)

a. An overall integrated leakage rateAof less thaa or equal to La,

,o .1~ pereeat: S)I weight ~f t:he contai:Ameat: air peF- ~4 ho1.1FS- at:

d&sig:a p~essl.1~& (47 Q peig) .

b. A combined leakage rate \ef less tRan or equal to 0.60 L~ for all penetrations and valves subject to Type B and C tests.-as-iae:c:itifiea is ~able 3.6 l, when piessurized te Pa. ~

cl.M.)~~*

APPLICABILITY: MODES 1, 2, 3 and 4.

f~L.~~

ACTION: T~~~

With either (a) the measured overall integrated containment leakage rate (1~ A ~)~

feJtseeei&§ 9.75 La~ or (b) with the measured combined leakage rate for all penetrations and valves subject to Types B and C tests e::teeeeaing G.ee Lat~J!.--

restore the l~akage rate(s) to within the limit(s) prior to increasing the '

Reactor Coolant System temperature above 200°F.

SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated as follows:

a. Type A tests shall be in accordance with 10CFR SG.54(0) in. ~

-eenf'ormenee wit-ft """"'PPB:c:ld~ d ef 3::0CPR so, OptiOB B, ltS:hJg t:he \

..,raetJ:;i.eds ane ~sieft.liZ of Res.11 1 atery St:iide 1.1'3, Septemaer 199;< *;

~10JHied ey appro~ed exem'2,tjgas. * ~ ~

~~~

b. Type B and C tests shall be conducted iB esaformaRse wiU1  : ~-f~
lls::ppendix J ef lOC~ se, ~t:ie:a A, with sas at d:esi~ pressaie LL~ {l;4 (4'1'. O J!!'sig) ~t:: ia~era.*alos 110 gzeatei t:ae:n 24 mont:as exeeJ!!lt fer I~ ~.~

~sts i:rnel*n,;ag a:tr le;::k:s 9 ~ 0 'n(J - I

c. Air locks shall be tested and demonstrated OPERABLE in seafef'lftanee wits Appendix .1 of 19CFR 56, Option A, pe1 Sat veillanee

~qauiz eu1e11L 4 . 6 . l. 3

  • SALEM - UNIT 2 3/4 6-2 Amendment No. Hi 6, 172

CCHTA!N~E~T SYSTE~S CONTAINMENT AIR LOCKS L:MITING CONDITION FOR OPERATION

3. 6. l. 3 Each containment air lock shall be OPERABLE illith:
a. Both doors closed except when the air lock is being used for r.or~al transit entry and exit through the containment, then at least or.e air lock door shall be closed, and

. ,/

b. An overall alr lock leakage rate *.o.t less t~aA eF eq~al tea.es L a~

OuigA ~******* (47.Q ~sig); ~~ ~ T~

APPLICABILITY: MODES l, 2, 3 and 4. u~ _ O. ()

ACTION:

a. With one containment air lock door inoperable:
1. Maintain at least the OPERABLE air lock door closed and either restore the inoperable air lock door to OPERABLE status witnin 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.

Z. Operation may then c5ntinue until performance of the next required overall air lock leakage test provided that the CPE.~BLE air lock door is verified to be locked closed at least once per 31 days.

3. Other-..ise, be in at least HOT STANDBY within the next six hours and in COLD SHUTDOWN within the follo~ing 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
4. The provisions of Specification 3.0.4 are not applicable.
b. ~ith the containment air lock inoperable, except as tbe result of an inoperable air lock door, maintain at least one air 1-:~-door c~osea:

restore the inoperable air lock to OPERABLE status. ***:n. 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 HOT STANDBY within the next six'** -s and in ::JLJ SHUTDOWN within tne following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE ~EQUIRE~ENTS

~. 6. i. 3 t:acn containment air lock. snal l be demonstrated OPERABLE:

SAL~'1 - UNII 2

  • , e CONTAINMENT SYSTEMS CONTAINMENT AIR LOCKS
3. ?r or to establishing contain"'9rtt integri y,
b. By conducting an overa-11 air l~ck leakage test lat desi §A

~reH~Fe f4+.-&j'91g) u1Et verHyi"g the everall air leakage

~te is witAiA its limit:

c. At least once per 6 111>ntl'ls by verifying that only one door each air *1ock can be opened at a time.
    • Tl'le 11mas~.-ea luka~ at tAe tut pressl:!re (> 10 psig) shall be cffliltfp11ed bj an ext'f!-1pglatiaA faet:or of 9.Tte deterP.1ir:1e wt:'tn u1e

..seal leakage now 1 ate .a~ld be if tested at eesigA press1.1r1 (47.~

JlS1g), T"'1s exb"apolated seal leaKage 1ate shall ~less t~aA oi-eqw1l tD e.61 La

  • J n** pPovis1eRa af SpecH1cat1ou 4.0.2 are fl)t- app11eable.
  • SALEM - UNIT 2 3/4 6-S Amendment No. 62

CONTAINMENT SYSTEMS CONTAINMENT STRUCTURAL INTEGRITY LIMITING CONDITIONS FOR OPERATION

===========================================================

3.6.1.6 The SLructural integrity of the containment shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.1.6.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With the structural integrity of the containment not conforming to =he above requirements, restore the structural integrity to within the limits 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 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

===========================================================

4.6.1.6.1 Containment Surfaces The structural integrity of the exposed accessible interior and exterior surfaces of the containment, including the liner plate, shall be determined by a via1.1al inspectien of these inufaee-s.

1The iRspection ahall b§ fierformed prio-r to the 'P:y15e A cerrtaimnent leakaqe rate

_test (:refprence Specification 4.3 l 2) to verif17 rro apparent changea in.-.

,.-appearance er other abna.i;mal degradatiofl. If the Type ,<>, test ia performed -&.::.

  • le 1'"oar inte. oals, cwo addi tienal i11spectieF12 2halr be performed at

~ppreximatel) equal intervals daring shutdowns bet~eefl Type A teats.

4.6.1.6.2 Reports Any abnormal degradation of the containment structure detected during the above required inspections shall be evaluated for reportability pursuant to 10CFR50.72 and 10CFR50.73. The evaluation shall be documented and shall include a description of the condition of the concrete, the inspection procedure, the tolerances on cracking, and the corrective action taken.

SALEM - UNIT 2 3/4 6-8 Amendment ~o.

ADMINISTRATIVE CONTROLS

===========================================================
  • d.

(vi) A procedure identifying (a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective action.

Backup Method for Determining Subcooling Margin A program which will ensure the capability to accurately monitor the Reactor Coolant System i?ubcooling Margin. This '*

program shall include the following:

(i) Training of personnel, and (ii) Procedures for monitoring

e. Postaccident Sampling A program* which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions. The program shall include the following:

(i) Training of personnel

  • (ii) Procedures for sampling and analysis, (iii) Provisions for maintenance of sampling and analysis equipment.

/

(

    • *It is acceptable if the licensee maintains details of the program in plant operation manuals.

SALEM - UNIT 2 6-19 Amendment No. 112

INSERT A 6.8.4.f Primary Containment Leakage Rate Testing Program A program shall be established, implemented, and maintained to comply with the leakage rate testing of the containment as required by 10CFR50.54(o) and 10CFR50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program", dated September 1995.

The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa, is 47.0 psig.

The maximum allowable containment leakage rate, La, at Pa, shall be 0.1% of primary containment air weight per day.

Leakage Rate Acceptance Criteria are:

a. Primary containment leakage rate acceptance criterion is less than or equal to 1.0 La. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are less than or equal to 0.6 La for Type B and Type C tests and less than or equal to 0.75 La for Type A tests;
b. Air lock testing acceptance criteria are:
1) Overall air lock leakage rate is less than or equal to 0.05 La when tested at greater than or equal to Pa,
2) Seal leakage rate less than or equal to 0.01 La per hour when the gap between the door seals is pressurized to 10.0 psig.

Test frequencies and applicable extensions will be controlled by the Primary Containment Leakage Rate Testing Program.

The provisions of Specification 4.0.3 will be applied to the Primary Containment Leakage Rate Testing Program.

  • 3/4.6 BASES CONTAINMENT SYSTEMS
==================================================================

3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.l CONTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the accident analyses. This restriction, in conjunction with the leakage rate limitation, will limit the site boundary radiation doses to within the limits of 10 CFR Part 100 during accident conditions.

3/4.6.1.2 CONTAINMENT LEAKAGE The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the accident analyses at the~ accident pressure, P . As an added conservatism, the measured overall integrated leakage rate/fs further limited to less than or equal to 0.75 L or less than or equal o 0.75 L, as applicable, during performance bf ~he periodic test t account for ~ossible degradation of the containment leakage barriers between leakage tests.

{r~ A tiA.'t)

The surveillance testing for measuring leakage rates are consistent with

.the- reqJJi remerits of AppeRciilE "J" eif 10 CFR 'E'art 50?. -tb. Cn.tt~ L~~ ~

  • ~@~.

3/4. 6.1. 3 CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and~containmont leak rate. Surveillance testing of the air lock seals provide assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests .

  • SALEM - UNIT 2 B 3/4 6-1

CONTAINMENT SYSTEMS BASES

==================================================================

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 differential with respect to the outside atmosphere of 3.5 psig, and 2) the containment peak pressure does not exceed the design pressure of 47 psig during the limiting pipe break conditions. The pipe breaks considered are LOCA and steam line breaks.

The limit of 0.3 psig for initial positive containment pressure is consistent with the accident analyses initial conditions.

The maximum peak pressure expected to be obtained from a LOCA or steam line break event is ~ 47 psig.

3/4.6.1.5 AIR TEMPERATURE The limitations on containment average air temperature ensure that the overall containment average air temperature does not exceed the initial temperature condition assumed in the accident analysis for a LOCA or steam line break. In order to determine the containment average air temperature, an average is calculated using measurements taken at locations within containment selected to provide a representative sample of the overall containment atmosphere.

3/4.6.1.6 CONTAINMENT STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment will be maintained comparable to the original design standards for the life of the facility. Structural integrity is required to ensure that the containment will withstand the design pressure. The visual inspections of the concrete and liner and the Type A leakage testvare sufficient to demo strate this capability. ~ ~~ L~

3/4.6.1.7 CONTAINMENT VENTILATION SYSTEM The containment purge supply and exhaust isolation valves are required to be closed during plant operation since these valves have not been demonstrated capable of closing during a LOCA. Maintaining these valves closed during plant operations ensures that excessive quantities of radioactive materials will not be released via the containment purge system.

SALEM - UNIT 2 B 3/4 6-2 Amendment No. 178

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