Text

Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B
	ML20100J759
Person / Time
Site:	Peach Bottom
Issue date:	02/15/1996
From:	; PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	;
Shared Package
ML20100J739	List: ML20100J736; ML20100J759;
References
	NUDOCS 9602290242
	Download: ML20100J759 (35)
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I ATTACHMENT 2 PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 l Docket Nos. 50-277 50-278 License Nos. DPR 44 DPR-56 l

TECHNICAL SPECIFICATIONS' AND BASES CHANGES l List of Attached Pages Units 2 and 3 ,

TS Pages 1.1-3, 3.6-2, 3.64, 3.6-16, 5.0-17, 5.0-17a, Bases 3.0-12, 3.6-1, 3.6-2, 3.6-3, 3.6-4, 3.5-5, 3.6-11, 3.6-12, 3.6-13,3.6-29,3.6-30 l l

l 9602290242 960215 PDR ADOCK 05000277 p PDR

i m - a Definitions 1.1 1.1 Definitions (continued)

-L, -The-maximum-aMowable-pr4 mary centai- ent leaks;e I rate, L shell--be 0.5% of ari=ary caat aia-aa+ $4r l Mght-p,,er-day-at-the-calculated-peak-contai ent l pr;;;r; (",}.

LEAKAGE LEAKAGE shall be:

1 l a. Identified LEAKAGE 1

i

1. LEAKAGE into the drywell, such as that from pump seals or valve packing, that is captured and conducted to a sump or collecting tank; or

2. LEAKAGE into the drywell atmosphere from sources that are both specifically located i and known either not to interfere with the i l operation of leakage detection systems or l not to be pressure boundary LEAKAGE;

b. Unidentified LEAKAGE l

All LEAKAGE into the drywell that is not identified LEAKAGE;

c. Total LEAKAGE Sum of the identified and unidentified LEAKAGE;

d. Pressure Boundary LEAKAGE l

LEAKAGE through a nonisolable fault in a Reactor Coolant System (RCS) component body, pipe wall, or vessel wall.

LINEAR HEAT GENERATION The LHGR shall be the heat generation rate per RATE (LHGR) unit length of fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length.

(continued) l PBAPS UNIT 2 1.1-3 Amendment No. M

. \

l Primary Containment 3.6.1.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.1.1 Perform required visual examinations and leakage rate testing except for primary QTE S" 2.0.2 :: n;t l

containme Knr lock testing, in :pplic;ble accordance with>10 Ci" 50, App;ndi J, -t--- N g p%c d,,,hinm ,4 as-medin-by-approved-exempt-ions.,

Leo t Rale. Tt5h"p The lee'eege rete accept;nce crit:rien is- In accordance p <1 n t,. Heeever, dur ng the "r:t i

it witW10Cr",50h

' IT*' starte? fell: ring t:: ting perfer...;d in f,pp:nd4* J, :: j

rd:n;; .ith 10 Ci", 50, f.pp:ndi: 2, :: ~^d!#ied by

dified by :;pr: = d ::;;pti:::, the ???-""ed i

-tire criteri 2re a^-"tiens %

leshtae 1 0.5'L rate ::: fype 0 and Type C tc;t:

T., the- t. Trem.ra @%;ad end 4 0,.75 L, fer th; Type A t;;t. Lc4%e httMahy e ffqHvem SR 3.6.1.1.2 Verify drywell to suppression chamber 24 months bypass leakage is equivalent to a hole s 1.0 inches in diameter. MQ

NOTE------ i Only required after two consecutive tests fail and i continues until two consecutive tests pass 12 ronths PBAPS UNIT 2 3.6-2 Amendment No. H e-

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Primary Containment Air Lock 3.6.1.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME 1

D. Required Action and D.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. ANQ 1

D.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months l

l SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.2.1 ------------------NOTES------------------

1. An inoperable air lock door'does not invalidate the previous successful performance of the overall air ock leakage test. a M ID

2. Results shall be ev uated against acceptance criteria ef-SR 3.6.1.1.1, 4- :::erdance with 10 CT", 50, A Apper. dix J, :: tedi# icd by appre"ed ext ption:.

Perform required primary containment air C- - - - NOT E - - - - -3" lo k leakage rate testing in accordance -S" 3.0.2 i: r.:t wit 10 CT", 50, Apper. dix J, :: ::difi:d -app 14cabis--

by :ppre"ed exemption:. q:---------- 7 Th: ::: pt:ne criterien for :f r 1 :k In accordance testin; Never-aM--a4r 100k 10:k:;; r:t: TitII'40 CT", 50, l 0000 Appendix J, :s v : W:: '=i then te:ted : "+ ' "A. =

m a4 rima su

,;;r i

-the Shc fri'*]YD [ r%rn.Contcuornt4 04% EbbNtIbn:

4hvfr/*1$fy (continued)

(str4ietaf Le%t f eum p h T esiT %

PBAPS UNIT 2 3.6-6 Amendment No. fte

o PCIVs 3.6.1.3 l

SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY l

SR 3.6.1.3.14 Verify leakage rate through each MSIV is Q"

s 11.5 scfh when tested at 2: 25 psig. 0 ; .;. NOTE--

--:: ratY

^;l!-fl: ;

k'T l In accordance 6 0 cra 50, the frintl a---- m , ,.

ConbietdyDNy EE"IEIE5 d Eh ~

Qg Tkkt9 :pp r:'::d -

pg, excepticr.:

SR 3.6.1.3.15 Verify each 6 inch and 18 inch primary 24 months containment purge valve and each 18 inch primary containment exhaust valve is blocked to restrict opening greater than the required maximum opening angle. ,

l SR 3.6.1.3.16 Replace the inflatable seal of each 48 months 6 inch and 18 inch primary containment purge valve and each 18 inch primary containment exhaust valve.

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l PBAPS UNIT 2 3.6-16 Amendment No. SM-

Prcgrams and Manuals 5.5 '

5.5 Programs and Manuals 5.5.11 Safety Function Determination Proaram (SFDP) (continued) I

1. A required system redundant to system (s) supported by the inoperable support system is also inoperable; or o

2. A required system redundant to system (s) in turn supported by the inoperable supported system is also inoperable; or l

l

3. A required system redundant to support system (s) for- '

the supported systems (b.1) and (b.2) above is also inoperable.

c. The SFDP identifies where a loss of safety function exists. ;

If a loss of safety function is determined to exist by this '

program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered. _

5.5.12 Primary Containment Leakaae Rate Testina Proaram A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(c) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. I This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, " Performance-Based Containment Leakage-Test Program," dated September 1995.

The peak calculated containment internal pressure for the design ,

basis loss of coolant accident, P., is 49.1 psig. l 4 The maximum allowable primary containment leakage rate, L., at P.,

I shall be 0.5% of primary containment air weight per day. I Leakage Rate acceptance criteria are:

a. Primary Containment leakage rate acceptance criterion is s 1.0 L . During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are s 0.60 L, for the Type B and Type C tests and s 0.75 L, for Type A tests; (continued)

, NEW l

l PBAPS UNIT 2 5.0-17 Amendment No. tit-i r

Programs and Manuals 5.5 N

5.5 Programs and Manuals 5.5.12 Primary Containment Leakaoe Rate Testino Procram (continued)

b. Air lock testing acceptance criteria are:

1) Overall air lock leakage rate is s 9000 sec/ min when tested at 2: P,. \

The provisions of SR 3.0.2 do not apply to the test frequencies specified in the Primary Containment Leakage Rate Testing Program. ;

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The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.

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PBAPS UNIT 2 5.0-17a Amendment No. 2M r

SR Appiicability B 3.0 BASES l SR 3.0.2 The 25% extension does not significantly degrade the l (continued) reliability that results from performing the Surveillance at ,

its specified Frequency. This is based on the recognition ;

that the most probable result of any particular Surveillance l being performed is the verification of conformance with the SRs. The exceptions to SR 3.0.2 are those Surveillances for which the 25% extension of the interval specified in the Frequency does not apply. These exceptions are stated in !

the individual Specifications. ? er7 :1 f ah;re ';" 3.^.2

'h <l::: r.et :nly-i:-:- ry:ilhr.:: aith ; frewe..cy er ";n secordance-wyth-10-CFW-50-Appendix J, as i. edified by

a-^-a"-" -"

The requirements of regulations take '

recedence ovei the TS.& The TS cenact in :nd of th::::1ve: 1 7)tr6ertphen a ht inttrved ext:ad : te:t interv:1 :pecified ir the reg"13tient: !

Th:r:f rt, the e ir ? "a+= in-the Freq"e.cy stat 4 ;,

is specSed g Aevu O mS 3 .en e n , o --. .m,u.

g ='"*****-*="-*'-rr*-'-'

As stated in SR 3.0.2, the 25% extension also does not apply 8 A n M 60+bt K and 't to the initial portion of a periodic Completion Time that P SK inthdt a M M +h* requires performance on a "once per..." basis. The 25%

SR *>,0, l extension applies to each performance after the initial

) performance. The initial performance of the Required fnejut*) Sg} bit# .An

- Action, whether it is a particular Surveillance or some

'3 n,y of f);ca other remedial action, is considered a single action with a eyampk ok on Uaf h mA single Completion Time. One reason for not allowing the 25%

extension to this Completion Time is that such an action Nk iB5h.o b usually verifies that no loss of function has occurred by Yg.g ,n g g tnrys 3accomplishes checking the status of redundant or diverse components or :

the function of the inoperable equipment in an i c, +he MC fo I#, 9 alternative manner.

tonfswtd W The provisions of SR 3.0.2 are not intended to be used

' frop 39M M O"#. repeatedly merely as an operational convenience to extend f Surveillance intervals (other than those consistent with

! aII jub)L*Ws t l dor % is refueHng intenals) or periodic Compledon Time intervals beyond those specified,

[k,geg gogg, rocMe ethns g rkfunn Nws. - 3.0.3 SR 3.0.3 establishes the flexibility to defer declaring

[ , SR affected equipment inoperable or an affected variable outside the specified limits when a Surveillance has not been completed within the specified Frequency. A delay period of up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified (continued)

PBAPS UNIT 2 B 3.0-12 Revision No, t

l Primary Centainment !

B 3.6.1.1 !

l B 3.6 CONTAINMENT SYSTEMS '

B 3.6.1.1 Primary Containment BASES 1

l BACKGROUND The function of the primary containment is to isolate and l contain fission products released from the Reactor Primary !

System following a Design Basis Accident (DBA) and to l confine the postulated release of radioactive material. The '

primary containment consists of a steel lined, reinforced concrete vessel (for shielding purposes), which surrounds "4 Peactor Primary System and provides an essentially leak

.lght barrier against an uncontrolled release of radioactive ai,wial to the environment.

The isolation devices for the penetrations in the primary containment boundary are a part of the containment leak tight barrier. To maintain this leak tight barrier:

a. All penetrations required to be closed during accident conditions are either:

1. capable of being closed by an OPERABLE automatic Containment Isolation System, or

2. closed by manual valves, blind flanges, or de-activated automatic valves secured in their closed positions, except as provided in LCO 3.6.1.3, " Primary Containment Isolation Valves (PCIVs)";

b. The primary containment air lock is OPERABLE, except as provided in LCO 3.6.1.2, " Primary Containment Air Lock"; and

c. All equipment hatches are closed.

This Specification ensures that the performance of the primary containment, in the event of a DBA, meets the assumptions used in the safety analyses of Reference 1.

SR 3.6.1.1.1 leakage rate requirements are in conformance with 10 CFR 50, Appendix J (Ref. 3), as modified by approved exemptions.

(continued)

PBAPS UNIT 2 B 3.6-1 Revision No..+-

Primary Containment B 3.6.1.1 BASES (continued) 3 AFPLICABLE The safety design basis for the primary containment is that SAFETY ANALYSES it must withstand the pressures and temperatures of the limiting DBA without exceeding the design leakage rate. ;

The DBA that postulates the maximum release of radioactive j material within primary containment is a LOCA. In the analysis of this accident, it is assumed that primary containment is OPERABLE such that release of' fission products to the environment is controlled by the rate of primary containment leakage.

Analytical metheds and assumptions involving the primary containment are presented in Reference 1. The safety analyses assume a nonmechanistic fission product release following a DBA, which forms the basis for determination of offsite doses. The fission product release is, in turn, based on an assumed leakage rate from the primary containment. OPERABILITY of the primary containment ensures that the leakage rate assumed in the s alyses is not exceeded.

m b s LOCA

'. The maximum allowable eakage rate for e primary containment (L ) is .5% by weight of the containment air per24hoursalthe aximum peak containment pressure (P 4

of 49.1 psig g er 0.75 by e:ight--ef th: ::nt:ir;;;t ;ir p,)re

' 2' h;;.c; :t .h: r:duced-pressure of P '25 p:i;). The value of P, (49.1 psig) is conservative with respect to the current calculated peak drywell pressure of 47.2 psig

, (Ref. 2).

Primary containment satisfies Criterion 3 of he NR 1 Statement, g 6 Rode LCO W DT% Crp'am9J Primary containment OP RABILITY is maintained by liTniting leakage to s 1.0 L , e cept prior to the first startup after performing _a required 10 CP, 50, App;; dix J, leakage test.

At tMs time,'* th: ::,; tin;d Typ: L' :nd C Mk:.;,; ; ;t b; 0.75 L .

i

}(Yg.g mitS vr)qst }qe 4 0.5 L , :nd th ;verall Tyr: A Mk:;; =t b; :In add chamber must be limited to ensure the pressure suppression function is accomplished and the suppression chamber bt W t-* pressure does not exceed design limits. Compliance with 1

this LCO will ensure a primary containment configuration, including equipment hatches, that is structurally sound and that will limit leakage to those leakage rates assumed in the safety analyses. .

(continued) 4 4

PBAPS UNIT 2 B 3.6-2 Revision No. &-

9

i l Primary Containment l 8 3.6.1.1 l

BASES 1

LCO Individual leakage rates specified for the primary (continued) containment air lock are addressed in LCO 3.6.1.2.

APPLICABILITY In MODES 1, 2, and 3, a DBA could cause a release of radioactive material to primary containment. In MODES 4 and 5, the probability and consequences of these events are reduced due to the pressure and temperature limitations of these MODES. Therefore, primary containment is not required to be OPERABLE in RODES 4 and 5 to prevent leakage of radioactive material from primary containment.

ACTIONS Ad In the event primary containment is inoperable, primary containment must be restored to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . The.I hour Completion Time provides a period of ,

time to correct the problem commensurate with the importance 1 of maintaining primary containment OPERABILITY during l MODES 1, 2, and 3. This time period also ensures that the '

probability of an accident (requiring primary containment OPERABILITY) occurring during periods where primary containment is inoperable is minimal.

B.1 and B.2 If primary containment cannot be restored to OPERABLE status within the required Completion Time, the plant must be brought to a MODE in which the LCO does not apply. To l achieve this status, the plant must be brought to at least MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and to MODE 4 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from fu?1 power conditions in an orderly mannor and without challenging plant systems.

SURVEILLANCE SR 3.6.1.1.1 tb (W(ep (mtoinrrul- L% key f

REQUIREMENTS % T6tr9 ro ram.

Maintaining the priiary containment OPERABLE requires compliance with the isual examinations and leakage rate bI* I. d....

!.9,"b,

, . .~.'.'l.C...1.."y,jju^re~tbetlir "I_'",b, !...S..a

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_~ ' $oek leakage testing (SR 3.6.1.2.1), or main steam isolation (continued)

PBAPS UNIT 2 B 3.6-3 Revision No.-e-

.' Primary Containment B 3.6.1.1 BASES SURVEILLANCE SR 3.6.1.1.1 (continued)

REQUIREMENTS valve leakage (SR 3.6.1.3.14), does not necessarily result in a failure of this SR. The impact of the failure to meet

=

these SRs must be evaluated against the Type A, B, and C tgtpfa9(pho/M acceptance criteria ofM 0 CFR 50, n;;;; dix J.

leakage prior to the first startup after performing a As left ung Rc4 7E5by required 10 trR 50, n;;;.di J, leakage test is required to be < 0.6 L for combined Type B and C leakage, and < 0.75 L, f'/ r% m , for overall Type 'A leakage. At all other times between required leakage rate tests, the acceptance criteria is based on an overall Type A leakage limit of s 1.0 L,. At s 1.0 L the offsite dose consequences are bounded by the assumptions of the safety analysis. The Frequency is

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ten:i ::) d : n:t :;;'y the /Nar du,wne,#

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SR 3.6.1.1.2 Maintaining the pressure suppression function of primary containment requires limiting the leakage from the drywell i to the suppression chamber. Thus, if an event were to occur that pressurized the drywell, the steam would be directed through the downcomers into the suppression pool. This SR is a leak test that confirms that the bypass area between the drywell and the suppression chamber is less than or equivalent to a ene-inch diameter hole (Ref. 4). This ensures that the laakage paths that would bypass the suppression pool are within allowable limits.

The leakage test is performed every 24 months. The 24 month Frequency was deve. loped considering that component failures that might have affected this test are identified by other primary containment SRs. Two consecutive test failures, however, would indicate unexpected primary containment degradation; in this event, as the Note indicates, a test shall be performed at a Frequency of once every 12 months until two consecutive tests pass, at which time the 24 month test Frequency may be resumed.

(continued)

PBAPS UNIT 2 B 3.6-4 Revision No. .

Primary Containment B 3.6.1.1

1 BASES (continued) l l

REFERENCES 1. UFSAR, Section 14.6.3.

2. Letter G94-PEPR-183, Peach Bottom Improved Technical Specification Project Increased Drywell and ,

Suppression Chamber Pressure Analytical Limits, from '

G.V. Kumar (GE) to A.A. Winter (PECO), August 23, 1994.

3. 10 CFR 50, Appendix .

, Op% 6

4. Safety Evaluation by the Office of Nuclear Reactor !

Regulation Supporting Amendment Nos. 127 and 130 to ~

Facility Operating License Nos. DPR-44 and DPR-56, dated February 18, 1988.

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( 6, NET R4-ol, RvLsm o, Indwtrg (maline Sol' i Tmp kmutty ferSonnue -8aseG Oy,,hn ob 10 o=R 1 act 50, /9 res> p dix K \

l (, , jwsr/aMS- 56.5 - M., *. Containme#

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$ystevn Leakage ~llsh'np 8 9 uiremcds." ,

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l PBAPS UNIT 2 B 3.6-5 Revision No.4"

Primary Containment Air Lock-B 3.6.1.2 BASES ACTICNS C.I. C.2. and C.3 (continued) limits. In many instances (e.g., only one seal per door has failed), primary containment remains OPERABLE, yet only 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months (according to LCO 3.6.1.1) would be provided to restore the air lock door to OPERABLE status prior to requiring a plant shutdown. In addition, even with the overall air lock leakage not within limits, the overall containment leakage rate can still be within limits.

Required Action C.2' requires that one door in the primary containment air lock must be verified closed. This action must be completed within the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time. This specified time period is consistent with the ACTIONS of LCO 3.6.1.1, which require that primary containment be i restored to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Additionally, the air lock must be restored to OPERABLE !

status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . The 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Completion Time is reasonable for restoring an inoperable air lock to OPERABLE status considering that at least one door is maintained closed in the air lock. .

l D.1 and D.2 ,

If the inoperable primary containment air lock cannot be restored to OPERABLE status within the associated Completion Time, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, the plant must be brought to at least MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and to MODE 4 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The allowed Completion Times are ,

reasonable, based on operating experience, to reach the !

required plant conditions from full power conditions in an orderly manner and without challenging plant systems.

SURVEILLANCE SR 3.6.1.2.1 REQUIREMENTS Maintainina Drimary containment air locks OPERABLE requires ,

compliance with the leakage rate test requirements or & I

& fr(mOf 10 CIR 50, App sdi; J (Ref.--2), as n dified by ;pp wicd enemp440s. This SR reflects the leakage rate testing M*,""j L A he requirements with respect to air lock leakage (Type B ,

A % TEs%g f y o**

1eakage tests). The acceptance criteria were established

% during initial air lock and primary containment OPERABILITY (continued) l PBAPS UNIT 2 B 3.6-11 RevisionNo.g

, . 1 Primary Containment Air Lock B 3.6.1.2 l

BASES

{

i i

SURVEILLANCE SR 3.6.1.2.1 (continued)

REQUIREMENTS testing. The periodic testing requirements verify that the l air lock leakage does not exceed the allowed fraction of the overall crimary containment leakage rate. The Frequency is gg (AjM required byP_0 "" 50, ".;;;;di 2 '".:f. 2), :: rdi d by go N5iY . 5

\ fywy rn. The SR has been modified by two Notes. Note I states that an inoperable air lock door does not invalidate the previous successful performance of the overall air lock leakage test.

This is considered reasonable since either air lock door is !

capable of nroviding a fission product barrier in the event ;

of a DBA. Note 2 % : i:n :dt d te thi SR, re-"! i ; the. J ffjl4i/ts M M b g: M t:b;: g :t:d y i.:tt{.g::jt. ,

it.,;. .f b OIY O \.....................'

n -

G bre cedtnt4 db SR 3.6.1.2.2 fr(ag, (odelorMid The air lock interlock mechanism is designed to prevent

. simultaneous opening of both doors in the air lock. Since LL M Np'i '

both the inner and outer doors of an air lock are designed

, to withstand the maximum expected post accident primary f}v en, 5. 5. g. g / containment pressure, closure of either door will support primary containment OPERABILITY. Thus, the interlock 0nSurts thttiht -

i feature supports primary containment OPERABILITY while the .

I Girlor)( N4 air lock is being used for personnel transit in and out of

/ ORM (i the containment. Periodic testing of this interlock

' demonstrates that the interlock will function as designed i

j [y 3Yiny)tN/mi/8/}

r and that simultaneous inner and outer door opening will not inadvertently occur. Due to the purely mechanical nature of

-f tlk M *'n N ' [, this interlock, and given that the interlock mechanism is b Mg ( fffnor only challenged when primary containment is entered, this test is only required to be performed upon entering primary g o n-ft,inem Il4N' E- containment, but is not required more frequently than 104 days when primary containment is de-inerted. The 184 day Frequency is based on engineering judgment and is considered adequate in view of other administrative controls available to operations personnel.

(continued)

PBAPS UNIT 2 B 3.6-12 Revision No. #

. - -. .._ - = .- _ __

l .

l Primary Containment Air Lock B 3.6.1.2 BASES (continued)

REFERENCES 1. UFSAR, Section 5.2.3.4.5.

l. ) () fivh 6 i

2. 10 CFR 50, Appendix JV'~

3. Letter G94-PEPR-183, Peach Bottom Improved Technical Specification Project Increased Drywell and Suppression Chamber Pressure Analytical Limits, from G.V. Kumar (GE) to A.A. Winter (PEco), August 23, 1994, i

l l

l .

l l

i 1

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l PBAPS UNIT 2 B 3.6-13 Revision No.4f

PCIVs B 3.6.1.3 BASES SURVEILLANCE SR 3.6.1.3.13 REQUIREMENTS (continued) This SR ensures that in case the non-safety grade instrument 1

air system is unavailable, the SGIG System will perform its design function to supply nitrogen gas at the required pressure for valve operators and valve seals supported by the SGIG System. The 24 month Frequency was developed

, considering it is prudent that this Surveillance be performed only during a plant outage. Operating experience has shown that these components will usually pass this Surveillance when performed at the 24 month Frequency.

Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.

SR 3.6.1.3.14 The analyses in Reference 1 are based on leakage that is

less than the specified leakage rate. Leakage through each MSIV must be s 11.5 scfh when tested at k Pt (25 psig). 24uk MSIV--leakage-rate-must--be verified to be in: :: rd:::: rith-the-le.k.v iust i qwir;;;.;nts of 10 CFR 50, ?.ppendix J (Ref.-3)cas-modified 4y-:ppr:;;d :=:;tter:. This ensures that MSIV leakage is properly accounted for in determining TI li p#lf ontainm c J1 the overall primary containment leakage rate. The Frequency is required blF"10 CTR 50, App;ndix J, as 2. edified L, Lenks /ddl ~IE5 hhp !??r:V d 2x^ 7t!*"!; th"!- SP 3 9 2 (""ich 311 "E "'*1"*"c7 V extensiens) d::: ::t :pply.

WO (G M, SR 3.6.1.3.15

, Verifying the opening of each 6 inch and 18 inch primary containment purge valve and each 18 inch primary containment exhaust valve is restricted by a blocking device to less than or equal to the required maximum opening angle specified in the UFSAR (Ref. 4) is required to ensure that the valves can close under DBA conditions within the tives in the analysis of Reference 1. If a LOCA occurs, the purge and exhaust valves must close to maintain primary containment leakage within the values assumed in the accident analysis. At other times pressurization concerns are not present, thus the purge and exhaust valves can be fully open. The 24 month Frequency is appropriate because the blocking devices may be removed during a refueling outage.

(continued) d PBAPS UNIT 2 B 3.6-29 Revision No.,B'

r

- PCIVs l B 3.6.1.3 l

1 BASES SURVEILLANCE SR 3.6.1.3.16 l REQUIREMENTS l (continued) The inflatable seal of each 6 inch and 18 inch primary containment purge valve and each 18 inch primary containment exhaust valve must be replaced every 48. months. This will allow the opportunity for replacement before gross leakage failure occurs. The 48 month Frequency is based on vendor recommendation and operational experience which shows that -l gross leakage normally does not occur when the inflatable seals are replaced on a 48 month Frequency.

REFERENCES 1. UFSAR, Chapter 14.

2. UFSAR, Table 7.3.1.

3 OF h" l

3. 10 CFR 50, Appendix J.

4. UFSAR, Table 7.3.1, Note 17.

'I PBAPS UNIT 2 B 3.6-30 Revision No. g

~

Definitions 1.1 1.1 Definitions (continued)

The e W aller:ble prie:ry centai rnt 1 2k2;c

-rate, L,, :P.:ll b; 0.6bef pr*=ry :::t:t =nt 21-weight per day-at ths cdculated--peak centai ent pr:::ere (P,).

LEAKAGE LEAKAGE shall be:

a. Identified LEAKAGE

1. LEAKAGE into the drywell, such as that from pump seals or valve packing, that is captured and conducted to a sump or collecting tank; or

2. LEAKAGE into the drywell atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE;

b. Unidentified LEAKAGE All LEAKAGE into the drywell that is not identified LEAKAGE;

c. Total LEAKAGE Sum of the identified and unidentified LEAKAGE;

d. Pressure Boundary LEAKAGE LEAKAGE through a nonisolable fault in a Reactor Coolant System (RCS) component body, pipe wall, or vessel wall.

LINEAR HEAT GENERATION The LHGR shall be the heat generation rate per RATE (LHGR) unit length of fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length.

(continued) l PBAPS UNIT 3 1.1-3 Amendment No. l W

Primary Containment 3.6.1.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.1.1 Perform required visual examinations and C ~ NOTE--

leakage rate testing except for primary S". 3.0.2 i: net-containment air lock testing, in !""lic:ble j accordance with*10 Cf" 50, App;ndix J,- C------------ 9 g p;,,. (,Wn. f :: ::dified by :ppr:ved ;x; pti:n:.

L@ r $eIdy h e4::h:;e rate acceptance ce4+=*4an 4' In accordance -

withfl0 CTR,50,'

to @. 4 1.0 L*. ll:::ver, during th: fir:t unit 3;;7;;p fell: wing t : ting perfer :d i- Appendix 2, -

-.accordance-with 10, CEIL 50,_AppenMv 1- == rediried by

-madtfied-by-approved ::::ptient, the-_ appreved

-4eakage-rate-acceptane; crit:ri: :r:

M-0.64;--foNhe-Type-B -:nd Type C to:t: W"-T

/4 fes.w^ Md"It

.nd 4 0.75 L, for th; Typ: A t::t. I hby Tidir19 0 vo m. . n SR 3.6.1.1.2 Verify drywell to suppression chamber 24 months bypass leakage is equivalent to a hole

s; 1.0 inches in diameter. A_N_Q

-----NOTE------

Only required after two consecutive tests fail and continues until two consecutive tests pass 12 months PBAPS UNIT 3 3.6-2 Amendment No.-el4-

Primary Containment Air Lock 3.6.1.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AtlQ D.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months 1

1 SURVEILLANCE REQUIREMENTS l

SURVERLANCE FREQUENCY ;

I SR 3.6.1.2.1 ------------------NOTES------------------ !

1. An inoperable air lock door does not !

invalidate the previous successful ;

performance of the overall air 1 !

leakage test. a licableto j i

2. Results shall be ev uated against acceptance criteria of SR 3.6.1.1.1, 1 is 5 ceMs e H th 10 Cr* 50, ^

?.;;::di:: 2, :: -^dified by 2;;rer:d

??--;t! rt Perform required primary containment air 6 -NOT W l dk leakage rate testing in accordance ';R 0.0.2 O r.:t witW10 CFR 50, ?.;;::di:: J, :: :di'i:d :;;1j::bl:

hy anneaund e-- 7ti ,;., g .. m .... g +

( Th: ::::;tence crit:ri: f:r :ir 1 :h In accordance 1 t:: ting i:, ._:::r:ll :f r leek 10:k:;; r:t:

1 __ > ..

Owit10 Cf" 50,

____... w w . _m.u w . -r r . . ..m. ,, ., , .

fb fr/inog Containmed 10% NJe (($$[$3$ 7 Tfstr$3 rom, EE5iis:: E g, fcfg,. (continued)

Con 1cdrimtav Lto

@te Tes% fwa PBAPS UNIT 3 .

3.6-6 Amendment No. 4tt

l PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.1.3.14 Verify leakage rate through each MSIV is s 11.5 scfh when tested at a: 25 psig. SR 3.0.2--i; c.d E I II I... [

1 1 j

- - - ~~ 4ccordance with 10 C." 50, l

.t}w ff/rY1Arp f.;;=di 2, =

Codiermd 18% 3N(($$ U"

=xti;m a 7Es*9 wPP V'*'

SR 3.6.1.3.15 Verify each 6 inch and 18 inch primary 24 months containment purge valve and each 18 inch !

primary containment exhaust valve is l blocked to restrict opening greater than !

the required maximum opening angle.

i SR 3.6.1.3.16 Replace the inflatable seal of each 48 months l 6 inch and 18 inch primary containment purge valve and each 18 inch primary containment exhaust valve.

1 i

l PBAPS UNIT 3 3.6-16 Amendment No. ett-

- - = - _ - - - - - - . - . - - . . _ - - . - .

Progra:s and Manuals i 5.5 1 l

5.5 Programs and Manuals 5.5.11 Safety Function Determination Procram (SFDP) (continued)

1. A required system redundant to system (s) supported by the inoperable support system is also inoperable; or

2. A required system redundant to system (s) in turn supported by the inoperable supported system is also inoperable; or

3. A required system redundant to support system (s) for the supported systems (b.1) and (b.2) above is also l inoperable.

c. The SFDP identifies where a loss of safety function exists.

If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LC0 in which the loss of safety function exists are ranuired to he entered. .

-5.5.12 Primary Containment Leakaae Rate Testina Proaram A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 3 CFR 50, 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 Leakage-Test Program," dated September 1995.

The peak calculated containment internal pressure for the design l basis loss of coolant accident, P., is 49.1 psig. !

The maximum allowable primary containment leakage rate, L., at P ,

shall be 0.5% of primary containment air weight per day.

Leakage Rate acceptance criteria are:

a. Primary Containment leakage rate acceptance criterion is s

1. 0 L, . During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are s 0.60 L, for the Type B and Type C tests and 5 /

( 0.75 L, for Type A tests; )

(continued)

_m NEW PBAPS UNIT 3 5.0-17 Amendment No.414-l

=

. Prcgrats and Manuals bl 5.5

~

l ~

5.5 Programs and Manuals l 5.5.12 Primary Containment Leakaae Rate Testina Proaram (continued)

b. Air lock testing acceptance criteria are:

j 1) Overall air lock leakage rate is s 9000 sec/ min when j tested at 2 P,.

The provisions of SR 3.0.2 do not apply to the test frequencies

!; specified in the Primary Containment Leakage Rate Testing Program.

I The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.

i i

i 1

PBAPS UNIT 3 5.0-17a Amendment No. 444-.

l I

SR Applicability l B 3.0 i i

BASES SR 3.0.2 The 25% extension does not significantly degrade the -

(continued) reliability that results from performing the Surveillance at ;

its specified Frequency. This is based on the recognition

. that the most probable result of any particular Surveillance !'

l being performed is the verification of conformance with the SRs. The exceptions to SR 3.0.2 are those Surveillances for

. which the 25% extension of the interval specified in the l

Frequency does not apply. These exceptions are stated in the individual Specifications. ^;; : - ,-h :f 3:r: "" 2.^." ]

a--, ... .- i m 4 _. c . . . 4 n . .,. . m . , r,.o n ..,. . or 4.

5hi;rddied 2 h l0 d" ",0, ".pp;;.dia 0, e; ddift'ed t,, )

y,,...ed e ; Aier.;." The requirements of regulations take l recedence over the TS.& The T* :::::t in ::d Of th: ;; h ; I h

~JBt 6t6./ en a ith i4 ^*I .;;t;;d : t::t ict:r"-! 00 !'t-d ia tha raa"1atiaaL l

es, }gsgfgrg,[y h

,rj j j g ,ig th: Fr:-":::" :t: tin-

$ 5hedied gg ce,nnd fobe$t "" "*' ""- rr------

8rhndd ha +be g and +bt As stated in SR 3.0.2, the 25% extension also does not apply 0 to the initial portion of a periodic Completion Time that

, S K intA u k ci d 8 D 10 g requires performance on a "once per..." basis. The 25%

extension applies to each performance after the initial f~rtqut9 3g.})

Sit 10 l performance. The initial performance of the Required i

Action, whether it is a particular Surveillance or some

.# /9n yr of f cabk fi !

'( ' 3 other remedial action, is considered a single action with a I gyamF) o& on t/0:/h h A single Completion Time. One reason for not allowing the 25% {

extension to this Completion Time is that such an action l usually verifies that no loss of function has occurred by

(([g96W,n N)0

+he M fo

%it5h M Ib N tms checking the status of redundant or diverse components or accomplishes the function of the inoperable equipment in an M"d alternative manner.

ton %wtd E- W Uk

.0.2 is not The provisions of SR 3.0.2 are not intended to be used ;

frognan ,9SK

repeatedly merely as an operational convenience to extend l O I }jg)e, 7Ws e#G/'M IS Surveillance intervals (other than those consistent with 1

pcAp p refueling intervals) or periodic Completion Time intervals ip# g g beyond those specified.

ol Mt-; mls, 3.0.3 / ~

lWe ~j5R SR 3.0.3 establishes the flexibility to defer declaring affected equipment inoperable or an affected variable outside the specified limits when a Surveillance has not been completed within the specified Frequency. A delay period of up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified (continued.).

l l

l 1

PBAPS UNIT 3 B 3.0-12 Revision No.Af j

---P

. Primary Containment B 3.6.1.1 B 3.6 CONTAINMENT SYSTEMS B 3.6.1.1 Primary Containment BASES l

l BACKGROUND The function of the primary containment is to isolate and contain fission products released from the Reactor Primary .

System following a Design Basis Accident (DBA) and to l confine the postulated release of radioactive material. The primary containment consists of a steel lined, reinforced concrete vessel (for shielding purposes), which surrounds the Reactor Primary System and provides an essentially leak tight barrier against an uncontrolled release of radioactive material to the environment.

The isolation devices for the penetrations in the primary i containment boundary are a part of the containment leak ,

tight barrier. To maintain this leak tight barrier: j

a. All penetrations required to be closed during accident l conditions are either:

1. capable of being closed by an OPERABLE automatic Containment Isolation System, or

2. closed by manual valves, blind flanges, or ,

de-activated automatic valves secured in their 1 closed positions, except as provided in l LCO 3.6.1.3, " Primary Containment Isolation Valves (PCIVs)"; ;

b. The primary containment air lock is OPERABLE, except as provided in LC0 3.6.1.2, " Primary Containment Air Lock"; and

c. All equipment hatches are closed.

l This Specification ensures that the performance of the primary containment, in the event of a DBA, meets the assumptions used in the safety analyses of Reference 1.

SR 3.6.1.1.1 leakage rate requirements are in conformance with 10 CFR 50, Appendix J Ref. 3), as modified by approved

, exemptions.

(continued)

^

PBAPS UNIT 3 B 3.6-1 Revision No.Af 1

a

. Primary Containment B 3.6.1.1 l

BASES (continued)

APPLICABLE The safety design basis for the primary containment is that l SAFETY ANALYSES it must withstand the pressures and temperatures of the '

limiting DBA without exceeding the design leakage rate.

The DBA that postulates the maximum release of radioactive i material within primary containment is a LOCA. In the 1 analysis of this accident, it is assumed that primary containment is OPERABLE such that release of fission products to the environment is controlled by the rate of primary containment leakage.

Analytical methods and assumptions involving the primary containment are presentcJ in Reference 1. The safety analyses assume a nonmechanistic fission product release following a DBA, which forms the basis for determination of <

offsite doses. The fission product release is, in turn, l based on an assumed leakage rate from the primary i containment. OPERABILITY of the primary containment ensures that the leakage rate assumed in the safety analyses is not exceeded, y h Q, gh i

The maximum allowabl eakage rate or the primary l containment (L is .5% by weight of the containment air per24hoursal)th maximum peak containment pressure (P,)

. of 49.1 psigier 0.75% by ::ight :f th: ::nt:i ::nt :fr p;r 24 h:;r; :t 'the-reduced-pres:Cr: f" (25 p;ig). The value of P, (49.1 psig) is conservative with respect to the l current calculated peak drywell pressure of 47.2 psig '

(Ref. 2).

Primary containment sat fies Criterion 3 of th_e_ NRC Dolicy Statement. g

% D1 s%fremtf LC0 Primary containment OPERABILITY is maintained by limiting leakage to :s; 1.0 L , xcept prior to the first startup after performino a required 10 0" 50, ^.ppend!" J, leakage test.

At this time,+th :::bine: Typ: B :nd C lenk:g mu t be 0 a 10:kage mt be ' O 75 L _

d[f bNE Ik :n a.5 LI , :nd th: :=r:11 Typ:ddition, the leakage from the drywell to th limfIS N I

chamber must be limited to ensure the pressure suppression function is accomplished and the suppression chamber bt' #p* pressure does not exceed design limits. Compliance with this LC0 will ensure a primary containment configuration, including equipment hatches, that is structurally sound and that will limit leakage to those leakage rates assumed in i the safety analyses. l (continued)

PBAPS UNIT 3 B 3.6-2 Revision No. /

e 5 *

Primary Containment B 3.6.1.1 BASES LC0 Individual leakage rates specified for the primary (continued) containment air lock are addressed in LC0 3.6.1.2.

APPLICABILITY In MODES 1, 2, and 3, a DBA could cause a release of radioactive material to primary containment. In MODES 4 and 5, the probability and consequences of these events are reduced due to the pressure and temperature limitations of these MODES. Therefore, primary containment is not required to be OPERABLE in MODES 4 and 5 to prevent leakage of radioactive material from primary containment.

ACTIONS A_,1 In the event primary containment is inoperable, primary containment must be restored to OPERABLE status within I hour. The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time provides a period of time to correct the problem commensurate with the importance of maintaining primary containment OPERABILITY during MODES 1, 2, and 3. This time period also ensures that the probability of an accident (requiring primary containment OPERABILITY) occurring during periods where primary containment is inoperable is minimal.

B.1 and B.2 If primary containment cannot be restored to OPERABLE status within the required Completion Time, the plant must be brought to a MODE in which the LC0 does not apply. To achieve this status, the plant must be brought to at least MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and to MODE 4 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.

the (Nav. Cobinmed Lta e SURVEILLANCE SR 3.6.1.1.1 Mit== "Tbh REQUIREMENTS j 1 I'rebc mm.

Maintaining the primtry containment OPERABLE requires compliance with the "isual examinations and leakage rate test requirements ofi'!? 5" 50, ^;;rdi 2 's";f C,.

'ndified by :ppr=:d su;ti=:. Failure to meet air lock leakage testing (SR 3.6.1.2.1), or main steam isolation (continued) 8 3.6-3 PBAPS UNIT 3 RevisionNo./

Primary Containment B 3.6.1.1 BASES SURVEILLANCE SR 3.6.1.1.1 (continued)

REQUIREMENTS valve leakage (SR 3.6.1.3.14), does not necessarily result in a failure of this SR. The impact of the failure to meet f these SRs must ha avaluated against the Type A, B, and C g g9 (egfar,g acceptance criteria of*10 CF". 50, ."4p;ndie J. As left leakage prior to the first startup after performing a Leka #sde7IM) required 10 Cra. 50, ^;;: dir 2, leakage test is required to be < 0.6 L for combined Type B and C leakage, and < 0.75 L, f ro m . foroverallTypeAleakage. At all other times between required leakage rate tests, the acceptance criteria is based on an overall Type A leakage limit of s 1.0 L . At s 1.0 L the offsite dose consequences are bounded by the assumptlons of the safety analysis. The Frequency is required by(0 CF" 50, ^.pp:ndix 2 (Ref. 2), :: med!# icd by

=narauad ava rtient. Mut, SR 2.0.2 (which__ ll a s i m uciivy-extenrien:) 40: net apply gg g ,.g SR 3.6.1.1.2 Maintaining the pressure suppression function of primary containment requires limiting the leakage from the drywell to the suppression chamber. Thus, if an event were to occur that pressurized the drywell, the steam would be directed through the downcomers into the suppression pool. This SR is a leak test that confirms that the bypass area between the drywell and the suppression chamber is less than or equivalent to a one-inch diameter hole (Ref. 4). This ensures that the leakage paths that would bypass the suppression pool are within allowable limits.

The leakage test is performed every 24 months. The 24 month Frequency was developed considering that component failures that might have affected this test are identified by other primary containment SRs. Two consecutive test failures, however, would indicate unexpected primary containment degradation; in this event, as the Note indicates, a test shall be performed at a Frequency of once every 12 months until two consecutive tests pass, at which time the 24 month test Frequency may be resumed.

(continued)

PBAPS UNIT 3 B 3.6-4 RevisionNo.g

, Primary Containment B 3.6.1.1 '

s BASES (continued)

REFERENCES 1. UFSAR, Section 14.6.3.

2. Letter G94-PEPR-183, Peach Bottom Improved Technical Specification Project Increased Drywell and Suppression Chamber Pressure Analytical Limits, from G.V. Kumar (GE) to A.A. Winter PECO), August 23, 1994.

3. 10 CFR 50, Appendix J< f ,O p % 6 l

4. Safety Evaluation by the Office of Nuclear Reactor Regulation Supporting Amendment Nos. 127 and 130 to Facility Operating License Nos. DPR-44 and DPR-56, dated February 18, 1988.

, d~ w

I 6, NEl 99-01, Reem O, Ind#p Mhoe SoM '

Tmy krnuky l'erkenne -80sep Ophn 1

s oy ;9 a=g pa,+ so,19ppe,,4,x 3,

(, , Ata3rj'aMS- 56.5 - FlW, " C#"Ya'"""#

% /

Syste.m Ledag Test $ <equinrneA"'

'~

.. , ~ . - ~ '

d J

PBAPS UNIT 3 8 3.6-5 RevisionNo.g

e !

Primary Containment Air Lock B 3.6.1.2 BASES ACTIONS C.1. C.2. and C.3 (continued) limits. In many instances (e.g., only one seal per door has failed), primary containment remains OPERABLE, yet only I hour (according to LCO 3.6.1.1) would be provided to ;

restore the air lock door to OPERABLE status prior to requiring a plant shutdown. In addition, even with the overall air lock leakage not within limits, the overall containment leakage rate can still be within limits.

Required Action C.2 requires that one door in the primary containment air lock must be verified closed. This action ,

must be completed within the I hour Completion Time. This l specified time period is consistent with the ACTIONS of )

LCO 3.6.1.1, which require that primary containment be restored to OPERABLE status within I hour.

Additionally, the air lock must be restored to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . The 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Completion Time is reasonable for restoring an inoperable air lock to OPERABLE )

status considering that at least one door is maintained 4 closed in the air lock. '

. D.1 and 0.2 If the inoperable primary containment air lock cannot be I restored to OPERABLE status within the associated Completion Time, the plant must be brought to a MODE in which the LC0 !

does not apply. To achieve this status, the plant must be brought to at least MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and to MODE 4 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The allowed completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.

SURVEILLANCE SR 3.6.1.2.1 REQUIREMENTS Maintaining primary containment air locks OPERABLE requires compliance with the leakaoe rate test requirements ofa At fring,n0 ontched C -/J-va-t CFR%= Skr Appendix This SR Jreflects iR ?. U, the::-: d!ff Odrate leakage bytesting

p;=0d LtcMay 8tdt. TEstiy requ'irements with respect to air lock leakage (Type B leakage tests). The acceptance criteria were established p3 during initial air lock and primary containment OPERABILITY (continued)

PBAPS UNIT 3 B 3.6-11 Revision No. g

I s e* '

o Primary Containment Air Lock B 3.6.1.2 BASES SURVEILLANCE SR 3.6.1.2.1 (continued)

REQUIREMENTS testing. The periodic testing requirements verify that the ;

air lock leakage does not exceed the allowed fraction of the l overall primary containment leakage rate. The Frequency is N guir (OdMmed ppre"ed Od by&M CTR ';0, App;; dix J(whi;h (Ref. 2), :s ;aedified by

. 4

-the frismr ex: ptt03 . Thus, S" 3.0.2 elle-5 T.m coimy i

/ _ . . , u. . . . ,s a...- .a

...im o v v The SR has been modified by two Notes. Note I states that f ('00 3r d n'1 an inoperable air lock door does not invalidate the previous y successful performance of the overall air lock leakage test.

This is considered reasonable since either air lock door is capable of 3roviding a fission product barrier in the event

^ *g - v- of a DBA. iote 2 % : been :dded to thi SR, requi" ng the aesults te be evahated--aga4nst-th ::: ptance criteri: cf NP'* , g resufb

M R 3.0.1.1.1. TMs-ensures-that

1d laaleana h l E= ' =0 0 2 '2 04 Otir bl(ltah$ y nt:!-- nt i t g: ra te,'- I y glbth b g, cedtr(a d SR 3.6.1.2.2 dimitd The air lock interlock mechanism is designed to prevent

, simultaneous opening of both doors in the air lock. Since f' h g % @ea t T dI toio

,f t both the inner and outer doors of an air lock are designed withstand the maximum expected post accident primary 5 containment pressure, closure of either door will support f(t)catem'g. g 5.11. gI .

6 f , primary containment OPERABILITY. Thus, the interlock endurtS . < feature supports primary containment OPERABILITY while the G ifI p'

}te)(y15 ) air lock is being used for personnel transit in and out of 4

ort)RTIM M A c/ the containment. Periodic testing of this interlock demonstrates that the interlock will function as designed

) 8 V

ghrmirli l and that simultaneous inner and outer door opening will not lF IO inadvertently occur. Due to the purely mechanical nature of

(

g ( p hi/&tI -} [} ,. this interlock, and given that the interlock mechanism is y$ and C /,.fy,g,ef only challenged when primary containment is entered, thist

, )mkge , a containment, but is not required more frequently than

( O nh'.# v ' 184 days when primary containment is de-inerted. The 184 day Frequency is based on engineering judgment and is considered adequate in view of other administrative controls available to operations personnel.

(continued)

PBAPS UNIT 3 B 3.6-12 RevisionNo./

\

^

i 6 Primary Containment Air Lock I B 3.6.1.2 l BASES (continued) l l

REFERENCES 1. UFSAR, Section 5.2.3.4.5.

,0phw B

2. 10 CFR 50, Appendix J.

3. Letter G94-PEPR-183, Peach Bottom Improved Technical Specification Project Increased Drywell and Suppression Chamber Pressure Analytical Limits, from ,

G.V. Kumar (GE) to A.A. Winter (PEco), August 23, !

1994. !

l l

PBAPS UNIT 3 B 3.6-13 RevisionNo.g

/

' PCIVs B 3.6.1.3 BASES l

SURVEILLANCE SR 3.6.1.3.13 REQUIREMENTS l (continued) This SR ensures that in case the non-safety grade instrument air system is unavailable, the SGIG System will perform its design function to supply nitrogen gas at the required pressure for valve operators and valve seals supported by the SGIG System. The 24 month Frequency was developed considering it is prudent that this Surveillance be performed only during a plant outage. Operating experience has shown that these components will usually pass this Surveillance when performed at the 24 month Frequency.

Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.

I SR 3.6.1.3.14 The analyses in Reference 1 are based on leakage that is less than the specified leakage rate. Leakage through each i MSIV must be :s 11.5 scfh when tested at 2: P (25 psig). .Th t l MS"! 1::k:ge rate-must be veri # icd te be i= accerd:= "ith the leakage-test-requirernt:-ef -10 CFD 9 appnad4v 3- l

("af. ':), es ;;dified by :ppr:ved ext:ption . This ensures 4 that MSIV leakage is properly accounted for in determining

.- 7 the overall or_imary containment leakage rate. The Frequency i

-t4pe frinloeg is required by'10 CFR 50, f.pp ndix J, = ::difi d by approved exceptic=; th=, SR 3.0.2 (which :"=: Freq= =y congyg g$ **

exten; ions) e = : = t :pp!y.

Mit IES SR 3.6.1.3.15 Verifying the opening of each 6 inch and 18 ' inch primary I containment purge valve and each 18 inch primary containment !

exhaust valve is restricted by a blocking device to less than or equal to the required maximum opening angle specified in the UFSAR (Ref. 4) is required to ensure that the valves can close under DBA conditions within the times in the analysis of Reference 1. If a LOCA occurs, the purge and exhaust valves must close to maintain primary containment leakage within the values assumed in the accident analysis. At other times pressurization concerns are not present, thus the purge and exhaust valves can be fully open. The 24 month Frequency is appropriate because the blocking devices may be removed during a refueling outage.

(continued) l PBAPS UNIT 3 8 3.6-29 RevisionNo./

/

~. . ,

F PCIVs B 3.6.1.3 BASES f

SURVEILLANCE SR 3.6.1.3.16 REQUIREMENTS (continued) The inflatable seal of each 6 inch and 18 inch primary containment purge valve and each 18 inch primary containment exhaust valve must be replaced every 48 months. This will allow the opportunity for replacement before gross leakage failure occurs. The 48 month Frequency is based on vendor recommendation and operational experience which shows that i

gross leakage normally does not occur when the inflatable seals are replaced on a 48 month Frequency.

REFERENCES 1. UFSAR, Chapter 14.

2. UFSAR, Table 7.3.1. g)7p3,3{$

3. 10 CFR 50, Appendix J.

4. UFSAR, Table 7.3.1, Note 17.

1 A

4 PBAPS UNIT 3 8 3.6-30 RevisionNo.,)f

ML20100J759

Text

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