ML20215F830
| ML20215F830 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 10/10/1986 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20215F827 | List: |
| References | |
| NUDOCS 8610160390 | |
| Download: ML20215F830 (19) | |
Text
.
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 degrees F to verify primary contain-and fuel is.in the reactor vessel ment integrity.
Primary 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 or the reactor placed in a may be performed at either cold shutdown condition within 49.1 psig or 25 psig, the 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 />) at 25 psig as the lesser of the following values:
I La (L m/L am) l L t
=
t where La = 0.5 percent of the primary contalment volume per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 49.1 psig.
-166-8610160390 861010~
PDR ADOCK 05000277 P
PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.A Primary Containment (Cont'd.)
4.7.A Primary Containment (Cont'd.)
l L
= measured ILR at 25 tm Psig (q )
l L""= measured ILR at 49.1 psig (g
), and l
L tm
< 0.7, otherwise l
L am Le =
La (P
/P, )b l
t where La = 0.5 percent of the primary contalment volume per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 49.1 psig.
P,
= peak accident pressure (Psig) l P'
= appropriately measured test pressures (psig) l
- c. The ILRT's shall be performed at the following minimum frequency:
1.
Prior to initial unit operation.
2.
After the preoperational 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, Lm and Lam shall be less t
than 0.75 Le and 0.75 L a for the reduced pressure tests and peak pressure tests, respectively.
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PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.A Primary 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.
If the acceptance criteria as specified in Section 4.7.A.2.d cannot be met during an ILRT, the ILRT shall be declared a failure and one of the following methods shall be used to perform a subsequent ILRT.
(1) If the post-repair leakage cannot be measured by local leak rate test methods, the identified leakage paths shall be repaired.
The subsequent ILRT shall be completed with the repaired leakage paths in service and the ILRT results shall meet the acceptance criteria specified in Section 4.7.A.2.d.
(2) If the post-repair leakage can be determined by local leak rate test methods, those leakage paths may be isolated or repaired during the ILRT.
For each leakage path that remains isolated during the subsequent ILRT, local leakage rates shall be measured after repairs are made.
The post-repair minimum pathway local leakage rates shall be added to the measured ILRT and the results shall meet the
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PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.A Primary Containment (Cont'd.)
4.7.A Primary Containment (Cont'd.)
acceptance criteria of Section 4.7.A.2.d.
The minimum pathway leakage is the smaller leakage rate of in-series valves tested individually, one-half the leakage rate for in-series valves tested simultaneously by pressurizing between the valves, and the combined leakage rate for valves tested in parallel.
t i
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,L'IMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.A Primary Containment (Cont'd.)
4.7.A Primary Containment (Cont'd.)
f.
Local leak rate tests (LLRT's) shall be performed on the primary containment testable penetrations and isolation valves in accordance with Tables 3.7.2, 3.7.3, & 3.7.4 at a pressure of 49.1 psig (except for the main steam isolation valves, see below) each operating cycle, but in no case 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 at intervals greater than two years.
If a total leakage rate of 11.5 scf/hr for any one main steamline isolation valve is exceeded, repairs ~and retest shall be performed 4
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.
-169-l
e PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.A Primary Containment (Cont'd.)
4.7.A Primary Containment (Cont'd.)
l 4
3.
Pressure Suppression h.
Drywell Surfaces Chamber - Reactor Build-ing Vacuum Breakers The interior surfaces of the drywell and torus shall l
a.
Except as specified in be visually inspected each 3.7.A.3.b below, two operating cycle for evi-pressure suppression dence 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 The pressure suppression psid.
chamber-reactor building vacuum breakers and assoc-b.
From and after the date lated instrumentation in-that one of the pressure cluding setpoint shall be suppression chamber-checked for proper reactor building vacuum operation every refueling breakers is made or found outage.
to be inoperable for any reason, reactor operation 4.
Drywell-Pressure Suppression is permissible only during Chamber-Vacuum Breakers the succeeding seven days unless such vacuum breaker a.
Each drywell-suppression is sooner made oeprable, chamber vacuum breaker provided that the repair shall be exercised through procedure does not violate an opening-closing cycle primary containment once a month.
l integrity.
l b.
When it is determined that a 4.
Drywell-Pressure Suppression vacuum breaker valve is Chamber Vacuum Breakers inoperable for opening at a time when 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-s
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PBAPS TABLE 3.7.2 TESTABLE PENETRATIONS WITH DOUBLE O-RINGS SEALS Pen No.
Notes N-1 Equipment (1)(2)(4)(6)
Access Hatch N-2
~ Equipment (1)(4)(7)(8) l Access and l
Personnel Air 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-2521B (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 N-212 Stop Check 13-9 (RCIC Stop Check)
~~
(1)(2)(4)(6)
(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) l
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o PBAPS TABLE 3.7.3 TESTABLE PENETRATIONS WITH TESTABLE BELLOWS Pen No.
Notes Pen No.
Notes l
N-7A Main (1)(2)(4)
N-13A RHR Pump (1)(2)(4)
Steam Line
'A' (6)
Discharge (6) l N-7B Main (1)(2)(4)
N-13B RHR Pump (1)(2)(4)
Steamline
'B' (6)
Discharge (6) l N-7C Main (1)(2)(4)
N-14 Reactor Water (1)(2)(4)
Steamline
'C' (6)
Cleanup Line (6) l N-7D Main (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 RHR Head Spray (1)(2)(4) l Line
'B' (6)
(6)
N-ll Steam Line to (1)(2)(4)
N-201A Suppression (1)(2)(4)
HPCI Turbine (6) through Chamber to (6)
N-20lH Drywell Vent N-12 RHR Shutdown (1)(2)(4)
Line Cooling (6)
Pump Suction
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-.-y
PBAPS TABLE 3.7.4 PRIMARY CONTAINMENT TESTABLE ISOLATION VALVES Pen No.
NOTES 7A to D AO-2-80A to D 1,2,3,4,5,9,11 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 14 MO-12-15 (Unit #2) 1,2,4,5,9,10 MO-12-15 (Unit #3) 1,2,4,5,9,11 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.-
=
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PBAPS TABLE 3.7.4 PRIMARY CONTAINMENT TESTABLE ISOLATION VALVES 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 #2); MO-3373 (Unit #3) 1,2,4,5 24 MO-2374 (Unit #2); MO-3374 (Unit #3) 1,2,4,5 25, AO-2502A (Unit #2); AO-3!02A (Unit #3) 1,2,4,5,9,12 205B AO-2505 (Unit #2); AO-3505 (Unit #3) 1,2,4,5 AO-2519 (Unit #2); AO-3519 (Unit #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 #2); 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 Tip Shear Valves 19 35F SV-109; Check Valve 1,2,4,5 37A to D CRD Insert; HCU 18 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 CRD Withdrawal; HCU 18 l
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 l
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 l
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PBAPS TABLE 3.7.4 PRIMARY CONTAINMENT TESTABLE ISOLATION VALVES Pen No.
NOTES 41 AO-2-39 1,2,4,5,9,11 AO-2-40 1,2,4,5 42 Check Valve 11-16 1,2,4,5 XV-14A,B 1,2,4,5,20 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 SlB 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 SlD SV-2980 (Unit #2); SV-3980 (Unit #3) 1,2,4,5 Check Valve 1,2,4,5 52F 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) 1,2,4,5,9,21 SV-8130A (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 #3) 1,2,4,5 SV-8101 (Unit #2); SV-9101 (Unit #3) 1,2,4,5
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O PBAPS TABLE 3.7.4 PRIMARY CONTAINMENT TESTABLE ISOLATION VALVES Pen No.
NOTES 205A AO-2502B (Unit #2); AO-3502B (Unit #3).
1,2,4,5,9,22 Check Valve 9-26B 1,2,4,5 210A MO-10-34B 1,2,4,5,9,11 Check Valve 10-19B,D 17*
210B MO-10-34A 1,2,4,5,9,11 Check Valve 10-19A, C 17*
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-10-38A 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 t
- 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 1
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 Check Valve 13-9; Check Valve 23-12 15 216 Check Valve 23-62 17 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
- Effective following completion of modifications scheduled during the 1987 Refueling Outage on Unit No. 2 (if necessary) and during the mid-cycle outage on Unit No. 3 or the next refueling outage on Unit No. 3, which comes first.
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c PBAPS TABLE 3.7.4 PRIMARY CONTAINMENT TESTABLE ISOLATION VALVES Pen No.
NOTES j
221 Check Valve 13-38 1,2,4,5 Check Valve 13-10 15 223 Check Valve 23-56 1,2,4,5 Check Valve 23-13 15 224 MO-14-26A; Check Valve 14-66A;(Unit 2) 17 Check Valve 14-66C; 3 Check Valves (Unit 2) 17 225 MO-14-71; MO-13-39 1,2,4,5 MO-13-41; MO-14-70 1,2,4,5,9,16 226A to D MO-10-13A to D; RV-10-72A to D 17 227 MO-23-57 1,2,4,5 MO-23-58 1,2,4,5,9,16 228A to D MO-14-7A to D 17 229 Check Valve 14-66B (Unit 2) 17 2 Check Valves (Unit 2 only) 17 Check Valve 14-66D (Unit 2) 17 230 Check Valve 13-29 17 233 MO-23-31 (Unit #2) 17 234 MO-14-26B (Unit 2) 17 2 Check Valves (Unit 2) 17 PASS Check Valve (Unit 2) 1,2,4,5 234A MO-14-26B (Unit 3) 17 3 Check Valves (Unit 3) 17 234B MO-14-26A (Unit 3) 17 2 Check Valves (Unit 3) 17 PASS Check Valve (Unit 3) 1,2,4,5 235 MO-23-31 (Unit 3) 17 236A Check Valve 14-66B (Unit 3) 17 Check Valve 14-66D (Unit 3) 17 236B Check Valve 14-66A (Unit 3) 17 Check Valve 14-66C (Unit 3) 17
-187b-l i
l
S 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.
1 (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)
Personnel Air Locks shall be tested at 6-month intervals.
(8)
The personnel air locks.are tested at 49.1 psig.
(9)
Identifies isolation valves that may be tested by applying pressure between the inboard and outboard valves.
(10)
Gate valve tested in reverse direction.
This is an exemption to 10 CFR 50, Appendix J.
Test acceptable since the normal force between the seat and the disc generated by stem action alone is greater than ten (10) times the normal force induced by test differential pressure.
This applies to the following valves:
MO-2-74 MO-10-31A, B MO-13-15 MO-10-18 MO-23-15 MO-12-15 (Unit #2)
MO-10-32
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d 8
PBAPS NOTES FOR TABLES 3.7.2 THROUGH 3.7.4 (Cont'd!
(11)
Globe valve which may be tested in reverse direction.
Test. acceptable since test pressure is applied under the valve seat.
This applies to the following valves:
AO-02-80A to D MO-12-15 (Unit #3)
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 sealing.
This applies to the following valves:
AO-2520 (3520)
AO-2506 (3506)
AO-2511 (3511)
AO-2521B (3521B)
AO-2502A (3502A)
(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)
These valves are locked closed except during ILRT's.
This is an exemption from 10 CPR 50, Appendix J.
(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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i
. ~
PBAPS NOTES FOR TABLES 3.7.2 THROUGH 3.7.4 (Cont'd)
(15)
These stop-check valves serve as block valves to allow testing of the outboard check valve.
The check function of these valves is not leak tested.
This applies to the following valves:
Check Valve 13-9 Check Valve 23-12 Check Valve 23-13 Check Valve 13-10 (16)
Gate valves tested in the reverse direction, since block valves and test connections necessary for " forward" testing do not exist.
Although these valves do not meet the " factor of ten" criteria described in Note 10, substantial margin does exist as indicated below:
Valve Normal Force Ratio MO-14-70 4.0 MO-23-58 1.2 MO-13-41 2.6 This is an exemption to the requirements of 10 CFR 50, Appendix J.
These valves will remain covered following all accidents.
Leakage in the proper direction through all valves is included in the Type A test results.
Leakage through MO-23-58 would be into a closed system designed to handle contaminated fluids following an accident per NUREG-0737, Item III.D.l.l.
(17)
Valves are stroke tested in conformance with the requirements of ASME Section XI, Subsection IWV, for j
Category B & C valves (as appropriate), in lieu of l
Appendix J, Type C, leak rate testing.
This is an exemption from 10 CFR 50, Appendix J, and is based upon the following reasons:
The lines discharge below the minimum torus water level and will thus have a water seal after an accident.
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PBAPS NOTES FOR TABLES 3.7.2 THROUGH 3.7.4 (Cont'd)
Any leakage through these valves will be into closed systems designed to remain operable and to handle contaminated fluids after an accident.
The integrity of these closed systems is assured by the leakage reduction and maintenance program developed in response to NUREG-0737, Item III.D.l.l.
These valves do not serve a safety function to limit the release of radioactivity to the environment.
Any leakage out of these systems will be into the reactor building, thus facilitating collection and treatment.
(18)
Individual valves on the CRD hydraulic control units are not Type C tested.
This is an exemption to 10 CPR 50, Appendix J.
Leakage is tested during the Type A and reactor vessel hydrostatic testing.
(19)
The TIP shear valve is not Type C tested because squib detonation is required for closure.
This is an exemption to 10 CFR 50, Appendix J.
These valves are located in small diameter (3/8") tubing lines. The possible leakage paths which include these valves are tested during the Type A tests.
(20)
Explosion valve tested in reverse direction.
Test acceptable since valve provides equivalent bi-directional sealing.
Valve is normally closed and opens only on SLCS actuation.
(21)
Inboard manual gate valve tested in the reverse direction.
Valve is locked closed except during refueling outages when containment breathing air is required.
This is an exemption from 10 CFR 50, Appendix J.
(22)
Butterfly valve tested in reverse direction.
Test acceptable since valve provides equivalent bi-directional sealing.
This applies to valves AO-2502B and AO-3502B.
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A' 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 based 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 after repairs are made to identified excessive leakage paths, provides a conservative assessment of containment leakage by ensuring that the containment integrated leakage rate satisfies the acceptance criteria of 10 CFR 50, Appendix J, once the testing is complete.
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 properly.
It is expected that the majority of the leakage from valves, penetrations and seals would 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.
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 l
MSIV's and in verifying that substantial degradation of these l
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 effect 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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4 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 listed in Note (11) for Tables 3.7.2 through 3.7.4, will be tested such that the test pressure is tending to lift the globe off its seat.
I I
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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