ML20083Q663

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Proposed Tech Spec Changes Updating Pages 167,168,169,184, 170,184a,186,187,188,185 & 192 Re 10CFR50,App J
ML20083Q663
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 04/19/1984
From:
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20083Q639 List:
References
NUDOCS 8404230183
Download: ML20083Q663 (16)
v • d • e


Text

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PBAPS LIMITING _ CONDITIONS __FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.A Primary _ Containment (Cont'd.) 4.7.A Primary Containment (Cont't.)

2. Primary containment integrity 2. Integrated Leak Rate Testing shall be maintained at all times when the reactor is critical or a. Integrated leak rate tests when the reactor water tempera- (ILRT's) shall be performed ture is above 212 F and fuel to verify primary contain-is in the the reactor vessel ment integrity. Primary j except while performing "open containment integrity is vessel" physics tests at power confirmed if the leakage levels not to exceed 5 Mw (t), rate does not exceed the equivalent of 0.5 percent
3. If the primary containment of the primary containment integrity is breached when volume per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at it is required by 3.7.A.2, 49.1 psig.

that integrity shall be re-established within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> b. Integrated leak rate tests hours or the reactor placed may be performed at either in a cold shutdown condition 49.1 psig or 25 psig, the within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. leakage rate test period, extending to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of retained internal pressure.

If it can be demonstrated to the satisfaction of those responsible for the acceptance of.the contain-ment structure that the leakage rate can be accu-rately determined during a shorter test period, the agreed-upon shorter period may be used.

Prior to initial operation, integrated leak rate tests must be performed at 49.1 and 25 psig (with the 25 psig test being performed prior to the 49.1 psig test) to establish the allowable leak rate (in percent of containment volume per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) i at 25 psig as the-lesser cf the following values:

, . (L, is 0.5 percent)

L - = 0.5 L t tm b

am B404230183 840419 -166- l PDR ADOCK 05000277 P pm ~

l I

,, , - - , - ~ . . - - ,- - r w- , - , ~- , , . - -

PBAPS l

LIMITIN,G CONDITIONS _FOR OPERATION SURVEILLANCE REQUIREMENTS l 3.7.A Primary _ Containment (Cont'd.) 4.7.A Primary Containment (Cont'd.) ll l where L un = measured ILR at 25 .g Psig (Pt ) e6 L am = measured ILR at 49.1 Psig (P a ), and {

L tm. < 0.7, otherwise ,

L am Lt = 0.5 Pt1b -

FY whers Pa = peak accident pressure l LPsig)

  • Pt = appropriately measured

]

test pressures (psig)

c. The ILRT's shall be performed at the following minimum frequency:
1. Prior to initial unit operation.
2. After the preoperational f leakage rate tests, a ,

set of three Type A ,

tests shall be performed at approximately equal intervals during each 10 year service period.

These intervals may be extended up to eight -

months if necessary to coincide with re-fueling outage. -

d. The allowable leakage rates, L tm. and' Iam , shall be less than 0.75 Lt and 0.75 La for the reduced pressure tests and peak pressure tests, respectively.

o

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PBAPS L_IMITING CONDITI,OJIS FOR OPERATION SURVEILLANCE REQUIREMENTS i 3.7.A Pri_ mary Containment (Cont'd.)

4.7.A Primary Containment (Cont'd.)

e. Except for the initial ILRT, all ILRT's shall be performed without any pre-liminary leak detection - >

surveys and leak repairs being performed between the containment inspection and the performance of the ILRT.n; While performing an ILRT, if excessive leakage is identified which will interfere with satisfactory completion of the test or result in the ILRT not meeting the acceptance criteria as specified in Section 4.7.A.2.d/ either of the following methods for determining the "as found" and "as left" condition of primary containment shall be used.

(1) If an ILRT cannot be satis-factorily completed due to excessive leakage through-identified leakage paths, those leakage paths may be isolated provided the leak-age through such paths can be determined by a local leak rate test. The ILRT shall be completed with the leakage paths isolated and the "as found" ILRT shall be declared a failure.

For each leakage path isolated during the ILRT, local leakage rates shall be measured and recorded before and after repairs are made to each leakage path. The pre-repair local .

leakage' rates ynall be added to the ILRT leakage rate, measured with the leak-paths isolated, and this shall be used to determine ,

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PBAPS SURVEILLANCE REQUIREMENTS LIMITING _ CONDITIONS FOR OPERATION 3.1.A Primary _ Containment (Cont'd.) 4.7.A Primary Containment (Cont'd.) '

V the "as found" condition of of primary containment.

The post-repair local leakage a rates shall be added to the ILRT leakage rate,

- measured with the leakage paths isolated, and this sum shall be used to determine the "as left" condition of primary containment.

(2) If an ILRT is completed with all identified leak-age paths in service, but the acceptance criteria of Section 4.7.A.2.d is not satisfied, the "as -

found" ILRT shall be de- .

clared a failure, any identified leakage paths i

shall be isolated provided the leakage through such paths can be determined by a local leak rate test, and another ILRT shall be con-ducted with the leakage paths isolated.

After repairs are made, local leakage rates shall be measured for each of those leakage paths isola-ted. The post-repair leak-age rates shall be added to the ILRT leakage rate, measured with the leakage paths isolated, and this sua shall be used to' determine the "as left" condition of primary con-ment. ,;

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_. .. . _ ~ -. ---- -__

LIMITING _COhDIT_ IONS FOR OPERATION __ SURVEILLANCE REQUIREMENTS 3.7.A- Primary _Containnent (Cont'd.) 4.7.A Primary Containment (Cont'd.)

f. Local leak rate tests (ILRT's) shall be performed on the primary containment _

testable penetrations and isolation valves at a i l pressure of 49.1 psig l (except for the main steam isolation valves, I see below) each operating l cycle, but in no case l at intervals greater than two years. Bolted '

- double-gasketed seals shall be tested whenever the seal is closed after being opened and at least once per operating cycle, but-in no case at intervals greater than two years.

The Main Steamline isola-tion valves shall be tested at a pressure of 25 psig for leakage during each refueling outage, but in no case -

4 at intervals greater than

! two years. If a total e leakage rate of 11.5 scf/hr for any one main steamline isolation valve is exceeded, repairs and retest shall be performed to correct the condition.

g. Continuous Leak Rate Monitor When the primary'contain-

, ment is inerted, the con-tainment shall be continu-ously monitored for gross leakage by review of the inerting system makeup requirements. This moni-toring system may be taken out-of-service for mainte-nance but shall be returned to service as soon as practicable..

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PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.A Primary _ Containment (Con t ' d) 4.7.A Primary Containment (Cont'd)

3. Pressure Suppression h. Drywell Surfaces ChamEer - Reactor Build-

_Ing vacuum Breakers The interior surfaces of the drywell and torus shall j a. Except as specified in be visually inspected each 3.7.A.3 b below , two operating cycle for evi-pressure suppression derce of deterioration. In chamber-reactor building addition, the external sur-vacuum breakers shall be faces of the torus below operable at all times the water level shall be whem primary containment inspected on a routine integrity is required, basis for evidence of The setpoint of the torus corrosion or leakage, differential pressure instrumentation which 3. Pressure Suppression actuates the pressure Chamber - Reactor Build suppression chamber-reactor ing Vacuum Breakers building vacuum breakers shall be 0.5 + 0.25

~ a. The pressure suppression psid. iated instrumentation in-cluding setpoint shall be

, b. From and after the date checked for proper that one of the pressure operation every refueling suppression chamber- outage, reactor building vacuum breakers is made or found 4. Drywell-Pressure Su:?pression to be inoperable for any Chamber-Vacuum Breacers reason, reactor operation is permissible only during a. Each drywell-suppression I the succeeding seven days chamber vacuum breaker unless such vacuum breaker shall be exercised through is sooner made oeprable, an opening-closing cycle provided that the repair once a month, procedure does not violate primary containment b. When it is determined that a integrity. vacuum breaker valve is 4.

inoperable for opening at a Drywell-Pressure Suppression time when Chamber vacuum Brea cers

a. When primary containment is required, all drywell-suppression chamber vacuum breakers shall be operable and positioned in the fully closed position (except during testing) except as specified in 3.7.A.4.b and c, below.
b. One drywell-suppression chamber' vacuum breaker may '

be non-fully closed so long as it is deter- l

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i PBAPS TABLE 3.7.2 TESTABLE _ PENETRATIONS WITH DOUBLE O-RINGS SEALS

-l Pen No. Notes N-1 Equipment (1)(2)(4)(6)

Access Hatch N-2 Equipment (1)(4)(8)

Access and Personnel Lock N-4 Drywell Head (1)(2)(4)(6)

Access Hatch N-6 CRD Removal (1)(2)(4){6)

Hatch N-25 AO-2520 (Unit #2); AO-3520 (Unit #3) (1)(2)(4)(6)

Purge System Valves N-26 AO-2506 (Unit #2); AO-3506 (Unit #3) (1)(2)(4)(6)

Purge System Valves N-35-A TIP System (1)(2)(4)(6) through N-35-G N-200A&B Suppression (1)(2)(4)(6)

Chamber Access Hatch N-205B AO-25218 (Unit #2); AO-3521B (Unit #3) Purge (1)(2)(4)(6)

AO-2502A (Unit #2); AO-3502A (Unit #3) System (1)(2)(4)(6)

N-205A AO-2502B (Unit #2); AO-3502B (Unit #3) . Valves , (1)(2)(4)(6)

N-212 Stop Check 13-9 (RCIC Stop Check) *

(1)(2)(4)(6)

N-213A&B Construction (1)(2)(4)(6)

Drain N-214 Stop Check 23-12" (HPCI Stop Check) (1)(2)(4)(6)

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PBAPS TABLE 3.7.3 TESTABLE PENETRATIONS WITH TESTABLE BELLOWS Pen No. Notes Pen No. Notes N-7A Primary (1)(2)(4) N-13A RHR Pump (1)(2)(4)

Steam Line 'A' (6) Discharge (6)

N-7B Primary (1)(2)(4) N-13B RHR Pump (1)(2)(4)

Steamline 'B' (6) Discharge (6)

N-7C Primary (1)(2)(4) N-14 Reactor Water (1)(2)(4)

Steamline 'C' (6) Cleanup Line (6)

N-7D Primary (1)(2)(4) N-16A Core Spray (1)(2)(4)

Steamline 'D' (6) Pump Discharge (6)

N-9A Feedwater (1)(2)(4) N-16B Core Spray (1)(2)(4)

Line 'A' (6) Pump Discharge (6)

N-9B Feedwater (1)(2)(4) N-17 RPV Head Spray (1)(2)(4)

Line 'B' (6) (6)

N-11 Steam Line to (1)(2)(4) N-201A Suppression (1)(2)(4)

!!PCI Turbine (6) through Chamber to '(6)

N-201H Drywell Vent N-12 RHR Shutdown (1)(2)(4) Line Pump Supply (6) 1 4

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l

. \

PBAPS l TABLE 3.7.4 PRIMARY CONTAINMENT TESTABLE ISOLATION VALVES NOTES Pen No.

7A to D AO-2-80A to D 1,2,3,4,5 AO-2-86A to D 1,2,3,4,5 8 MO-2-74 1,2,4,5,9,10 MO-2-77 1,2,4,5 9A MO-23-19; MO-2-38A 1,2,4,5 Check Valves 2-28A and 2-96A 1,2,4,5 9B MO-13-21; MO-2-38B; MO-12-68 1,2,4,5 Check Valves 2-28B and 2-96B 1,2,4,5 10 MO-13-15 1,2,4,5,9,10 MO-13-16 1,2,4,5 11 MO-23-15 1,2,4,5,9,10 MO-23-16 1,2,4,5 AO-4807 (Unit #2) 1,2,4,5 12 MO-10-18; 1,2,4,5,9,10 MO-10-17 1,2,4,5 13A MO-10-25B; AO-10-46B; AO-10-163B* 1,2,4,5 13B MO-10-25A; AO-10-46A; AO-10-163A* 1,2,4,5 F

14 MO-12-15 1,2,4,5,9,10 MO-12-18 1,2,4,5 16A MO-14-12B; AO-14-13B; AO-14-15B*, ** 1,2,4,5 16B MO-14-12A; AO-14-13A; AO-14-15A*, ** 1,2,4,5 17 MO-10-32 1,2,4,5,9,10 MO-10-33 1,2,4,5 18 AO-20-82 1,2,4,5,9,11 AO-20-83 1,2,4,5 19 AO-20-94 1,2,4,5,9,11 AO-20-95 1,2,4,5

. 21 Service Air System Inner Globe Valve 1,2,4,5,9,11 Service Air System Outer Globe Valve 1,2,4,5

  • Effective following the next Refueling Outage on Unit Nos. 2 & 3.
    • Effective following the next Refueling Outage subsequent to the l comp 1'etion of modifications on Unit 3 approved by Amendment No.

l l -185-l L

PBAPS TABLE 3.7.4 PRIMARY CONTAINMENT TESTABLE ISOLATION VALVES l

Pen No. NOTES .

22 AO-2969A (Unit #2); AO-3969A (Unit #3) 1,2,4,5 Check Valve 1,2,4,5 23 MO-2373 (Unit 42); MO-3373 (Unit #3) 1,2,4,5 24 MO-2374 (Unit 52); MO-3374 (Unit #3) 1,2,4,5 25, AO-2502A (Unit #2); AO-3502A (Unit #3) 1,2,4,5,9 205B AO-2505 (Unit #2); AO-3505 (Unit #3) 1,2,4,5 AO-2519 (Unit #2); AO-3519 (Unic #3) 1,2,4,5 AO-2520 (Unit #2); AO-3520 (Unit #3) 1,2,4,5,9,12 AO-2521A (Unit #2); AO-3521A (Unit #3) 1,2,4,5 AO-2521B (Unit #2); AO-3521B (Unit #3) 1,2,4,5,9,12 AO-2523 (Unit #2); AO-3523 (Unit #3) 1,2,4,5 Check Valve 9-26A; Two Check Valves 1,2,4,5 26 AO-2506 (Unit #2); AO-3506 (Unit #3) 1,2,4,5,9,12 AO-2507 (Unit #2); AO-3507 (Unit #3) 1,2,4,5 AO-2509 (Unit #2); AO-3509 (Unit #3) 1,2,4,5,9,11 AO-2510 (Unit #2); AO-3510 (Unit #3) 1,2,4,5 AO-4235 (Unit #2); AO-5235 (Unit #3) 1,2,4,5 SV-2671G (Unit #2); SV-3671G (Unit #3) 1,2,4,5 SV-2978G (Unit 52); SV-3978G (Unit #3) 1,2,4,5 SV-4960B (Unit #2); SV-5960B (Unit #3) 1,2,4,5 SV-4961B (Unit #2); SV-5961B (Unit #3) 1,2,4,5 SV-4966B (Unit #2); SV-5966B (Unit #3) 1,2,4,5 SV-8100 (Unit #2); SV-9100 (Unit #3) 1,2,4,5 SV-8101 (Unit #2); SV-9101 (Unit #3) 1,2,4,5 32C, D ILRT System Two Globe Valves 1,2,4,5,13 35A to E TIP Ball Valves 1,2,4,5 35F SV-7-113; Check Valve 1,2,4,5 38 CV-3-32A; CV-3-32B; CV-3-33 1,2,4,5 CV-3-35A; CV-3-35B; CV-3-36 1,2,4,5 39A MO-10-31B 1,2,4,5,9,10~

MO-10-26B 1,2,4,5 SV-4949B (Unit #2); SV-5949B (Unit #3) 1,2,4,5 Check Valve 1,2,4,5 39B MO-10-31A 1,2,4,5,9,10 MO-10-26A 1,2,4,5 SV-4949A_(Unit #2); SV-5949A (Unit #3) 1,2,4,5

' Check Valve 1,2,4,5 41 AO-2-39 1,2,4,5,9,11 AO-2-40 -1,2,4,5

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PDAPS

~ '

TABLE 3.7.4 PRIMARY CONTAINMENT TESTABLE ISOLATION VALVES Pen No. NOTES -

42 Check Valve 11-16; XV-14A,B 1,2,4,5 47 SV-8130B (Unit #2); SV-9130B (Unit #3) 1,2,4,5 Check Valve 1,2,4,5 51A SV-2671E (Unit #2); SV-3671E (Unit #3) 1,2,4,5 SV-2978E (Unit #2); SV-3978E (Unit #3) 1,2,4,5 513 SV-2671D (Unit #2); SV-3671D (Unit #3) 1,2,4,5 SV-2978D (Unit #2); SV-3978D (Unit #3) 1,2,4,5 51C SV-2671C (Unit #2); SV-3671C (Unit #3) 1,2,4,5 SV-2978C (Unit #2); SV-3978C (Unit #3) 1,2,4,5 SV-4960C (Unit #2); SV-5960C (Unit #3) 1,2,4,5 SV-4961C (Unit #2); SV-5961C (Unit #3) 1,2,4,5 SV-4966C (Unit #2); SV-5966C (Unit #3) 1,2,4,5 SV-8101 (Unit #2); SV-9101 (Unit #3) 1,2,4,5 51D SV-2980 (Unit #2); SV-3980 (Unit #3) 1,2,4,5 Check Valve 1,2,4,5 52P AO-2969B (Unit #2); AO-3969B (Unit #3) 1,2,4,5 Check Valve 1,2,4,5 53 MO-2201B (Unit #2); MO-3201B (Unit #3) 1,2,4,5 54 MO-2200B (Unit #2): MO-3200B (Unit #3) 1,2,4,5 55 MO-2200A (Unit #2); MO-3200A (Unit #3) 1,2,4,5 56 MO-2201A (Unit #2); MO-3201A (Unit #3) 1,2,4,5 57 AO-2-316 1,2,4,5,9,11 AO-2-317 1,2,4,5 102B Breathing Air System - 2 Gate Valves (Unit #3) 1,2,4,5,9 SV-8110A (Unit #2); SV-9130A (Unit #3) 1,2,4,5 Check Valve 1,2,4,5.

203 SV-2671B (Unit #2); SV-3671B (Unit #3) 1,2,4,5 SV-2978B (Unit #2); SV-3978B (Unit #3) 1,2,4,5 SV-4960D (Unit #2); SV-5960D (Unit #3) 1,2,4,5 SV-4961D (Unit #2); SV-5961D (Unit #3) 1,2,4,5 SV-4966D (Unit $2); SV-5966D (Unit < 1) 1,2,4,5 SV-8101 (Unit #2); SV-9101 (Unit 3) 1,2,4,5 205A AO-2502B (Unit #2); AO-3502B (Unit #3) 1,2,4,5,9,12 Check Valve 9-26B 1,2,4,5

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PBAPS I' l TABLE 3.7.4 PRIMARY CONTAINMENT TESTABLE ISOLATION VALVES Pen No. NOTES -

210A MO-10-34B 1,2,4,5,9,11 210B MO-10-34A 1,2,4,5,9,11 211A MO-10-38B 1,2,4,5,9,11 MO-10-39B; MO-10-34B; Check Valve 1,2,4,5 SV-4951B (Unit #2); SV-5951B (Unit #3) 1,2,4,5 211B MO-10-30A 1,2,4,5,9,11 MO-10-39A; MO-10-34A; Check Valve 1,2,4,5 SV-4951A (Unit #2); SV-5951A (Unit #3) 1,2,4,5 212, AO-4240 (Unit #2); AO-5240 (Unit #3) 1,2,4,5,9,11 214, AO-4241 (Unit #2); AO-5241 (Unit #3) 1,2,4,5 217B AO-4247 (Unit #2); AO-5247 (Unit #3) 1,2,4,5,9,11 AO-4248 (Unit #2); AO-5248 (Unit #3) 1,2,4,5 MO-4244 (Unit #2); MO-5244 (Unit #3) 1,2,4,5,14 MO-4244A (Unit #2); MO-5244A (Unit #3) 1,2,4,5,14 Check Valve 13-50; Check Valve 23-65 1,2,4,5 1 218A AO-2968 (Unit #2); AO-3968 (Unit #3) 1,2,4,5 Check Valve 1,2,4,5 218B SV-2671A (Unit #2); SV-3671A (Unit # 3) 1,2,4,5 SV-2978A (Unit #2); SV-3978A (Unit #3) 1,2,4,5 218C ILRT System-Two Globe Valves 1,2,4,5,13 219 AO-2511 (Unit #2); AO-3511 (Unit #3) 1,2,4,5,9,12 AO-2512 (Unit #2); AO-3512 (Unit #3) 1,2,4,5 AO-2513 (Unit #2); AO-3513 (Unit #3) 1,2,4,5,9,11 AO-2514 (Unit #2); AO-3514 (Unit #3) 1,2,4,5 SV-2671F (Unit #2); SV-3671F (Unit #3) 1,2,4,5 SV-2978F (Unit #2); SV-3978F (Unit #3) 1,2,4,5 SV-4960A (Unit #2); SV-5960A (Unit #3) 1,2,4,5 SV-4961A (Unit #2); SV-5961A (Unit #3) 1,2,4,5 SV-4966A (Unit #2); SV-5966A (Unit #3) 1,2,4,5 SV-8101 (Unit #2); SV-9101 (Unit #3) 1,2,4,5 221 Check Valve 13-38 1,2,4,5 223 Check Valve 23-56 1,2,4,5 225 MO-14-71; MO-13-39 1,2,4,5 1 227 MO-23-57 1,2,4,5

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PBAPS NOTES FOR TABLES 3.7.2 THROUGH 3.7.4 (1) Minimum test duration for all valves and penetrations listed is one hour.

(2) Test pressures shall be at least 49.1 psig for all valves and penetrations except MSIV's which are tested at 25 psig.

(3) MSIV's acceptable leakage is 11.5 scfh/ valve of air.

(4) The total acceptable leakage for all valves and penetrations other than the MSIV's is 0.60 La. MSIV leakage is excluded from this total.

(5) Local leak tests on all testable isolation valves shall be performed at intervals no greater than 2 years.

(6) Local leak tests on all testable penetrations shall be performed at intervals no greater than 2 years.

(7) Deleted. l (8) The personnel air locks are tested at 49.1 psig.

(9) Identifies isolation valves that are tested by applying pressure between the inboard and outboard valves.

(10) Gate valve tested in reverse direction. Test acceptable since the normal force between the seat and the disc generated by stem action alone is greater than ten (10) timos the normal force induced by test differential pressure. This applied to the following valves:

MO-2-74 MO-10-31A, B MO-13-15 MO-10-18 MO-23-15 MO-12-15 MO-10-32 h

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PBAPS NOTES FOR TABLES 3.7.2 THROUGH 3.7.4 (Cont'd)

(11) Globe valve tested in reverse direction. Test acceptable since test pressure is applied under the valve seat. This applies to the following valves:

AO-4240 (5240) AO-20-94 AO-4247 (5247) AO-2509 (3509)

MO-10-38A and B AO-2-39 MO-10-34A and B AO-2-316 AO-20-82 AO-2513 (3513)

Inner manual valve on penetration N-21.

(12) Butterfly valve tested in reverse direction. Test acceptable since valve is equipped with inflatable seals which provide equivalent bi-directional saaling. This applies to the following valves:

AO-2520 (3520) AO-2506 (3506)

AO-2511 (3511) AO-2521B (3521B)

AO-2502A and B (3502A and B)

(13) Manual globe valves tested in reverse direction. This applies to valves on the following penetrations:

N-32C (two valves)

N-218C (two valves)

N-32D (two valves)

(14) Gate valve utilized for containment isolation in both directions. Test performed only in one direction. Valve normal force ratio is 17.9. Leakage path is between

, separate torus penetrations only.

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T 3.7.A & 4.7.A BASES (Cont'd.)

The primary containment leak rate test frequency is based on maintaining adequate assurance that the leak rate remains within the specification. The leak rate test frequency is ba?,ed on the NRC guide for developing leak. rate testing and surveillance of reactor containment vessels.

The method for correcting measured containment integrated leakage rates based upon local leakage measurements, taken before and after repairs are made to identified excessive leakage paths, provides a conservative assessment of containment leakage by satisfying two objectives. First, by ensuring that the containment integrated leakage rate satisfies the acceptance criteria of 10 CFR 50, Appendix J, once the testing-is complete. Second, by ensuring that the "as found" condition of primary containment, i.e. before repairs are made, is determined for the purpose of establishing the subsequent test frequency in accordance with Appendix J.

The penetration and air purge piping leakage test frequency, along with the containment leak rate tests, is adequate to allow detection of leakage trends. Whenever a bolted double-gasketed penetration is broken and remade, the space between the gaskets is pressurized to determine that the seals are performing pro;3rly. It is expected that the majority of the leakage from valves, penetrations and seals vould be into the reactor building. However, it is possible that leakage into other parts of the facility could occur. Such leakage paths that may affect significantly the consequences of accidents are to be minimized. l The Main Steamline Isolation Valves (MSIV's) are angled in the main steam lines in order to afford better sealing in the direction of accident pressure. This being the case, local leak rate testing at a reduced pressure of 25 psig results in a conservative determination of the actual leakage through these valves. The 11.5 scf/hr acceptance criteria is effective and reliable.in determining the status of the MSIV's and'in verifying that substantial degradation of these valves has not occurred since the last Integrated Leakage Rate Test (ILRT). The 11.5 scf/hr criteria is likewise conservative because'of the reduced test pressure. -

Additionally, the leakage path through the MSIV's is' included during an ILRT: and therefore, the offect of this leakage on containment integrity is taken into account. For these-reasons, the leakage through the MSIV's is excluded from the limit of 0.6 La for-the combined leakage rate for penetrations and valves subject to local leak rate tests.

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l l

. 3.7.A & 4.7.A BASES (Cont'd.)

Table 3.7.4 identifies certain isolation valves that are tested by pressurizing the volume between the inboard and outboard isolation valves. This results in conservative test results since the inboard valve, if a globe valve, will be tested such that the test pressure is tending to lift the globe off its seat.

The primary containment pre-operational test pressures are based upon the calculated primary containment pressure response in the event of a loss-of-coolant accident. The peak drywell pressure would be about 49.1 psig which would rapidly reduce to 27 psig following the pipe break.

Following the pipe break, the suppression chamber pressure rises to 27 psig, equalizes with drywell pressure and therefore, rapidly decays with the drywell pressure decay.

The design pressure of the drywell and suppression chamber is 56 psig. Based on the calculated containment pressure response discussed above, the primary containment pre-operational test pressures were chosen. Also, based on the primary containment pressure response and the fact that the drywell and suppression chamber function as a unit, the primary containment will be tested as a unit rather than the individual components separately.

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