ML20085M715

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Amends 164 & 167 to Licenses DPR-44 & DPR-56,respectively, Changing TS Re Primary Reactor Containment Leakage Testing
ML20085M715
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 10/23/1991
From: Chris Miller
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20085M721 List:
References
NUDOCS 9111120121
Download: ML20085M715 (38)
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UNITED STATES

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NUCLEAR REGULATORY COMMISSION

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WASHINGTON. D. C. 205LS oA

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PHILADELPHIA ELECTRIC COMPANY P UBL I C~$ E R V I C E L Littkl t' AWBAF [5MP ANY DELliAPW) DREK'AW[]Bfit't0R AW-

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D_0CKET t10_. 50_-277 PEACH BOTTOM ATOMIC POWER STATION, UNIT N0_._2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 164 License No. DPR-44 1.

The f:uclear Regulatory Concission (the Commission) has found that:

A.

The application for amendment by Philadelphia Electric tempany, et.

al. (the licensee) dated i:ovember 18, 1976 and supplemented April 19, 1984, October 10, 1986, April 21 and June 23, 1988 and toay 17, 1991, con: plies with the standards and requiren<ents of the Atomic Energy Act of 1954, as arrended (the Act), and the Conrission's rules and regulations set forth in 10 CFR Chapter 1.

B.

The f acility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Conrission; C.

There is reasonable assurance (i) that the activities authorized by this ar.endnent can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in corrpliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health or safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

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2.

Accor'dingly, the license is amended by changes to the Technical l

Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. DPR-44 is hereby an; ended to read as follows:

l l-9111120121 911023 DR ADOCK 0500 7

(T)

, Technical Specifications The Ter.hnical Specifications contained in Appendices A and B, as l

revised through Amendtrent No.164, are hereby incorporated in the license. PECO shall operate the facility in accordance with the l

Technical Specifications.

3.

This license arnendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISS10fl h4dh Ub Charles L. Miller, Director Project Directorate 1-2 Division of Reactor Projects - 1/11 Office of f:uclear Reactor Regulation Attachn ent :

Cher.ges to the Technical Specifications Cate of Isst.ence:

October 23, 1991 l

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4 ATTACHMENT TO LICENSE'AMEt;DriENT tl0. 164 ff.C,1L,1],Y,,0f,Ep,A]JNG LICENSE N,0. OPR.44 DOCKET NO. 50 277 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicateo by marginal lines.

Remove insert 166 166 167 167 168 168 169 169 170 170 184 184 184a 185 185 18F.

186 187 187 187a 187b 188 188 188a 188b 188c i

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e PBAPS U71ts 2 and J LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 4.7.A P'imary Containment (Cont'd.)

3.7.A Primary Containment (Cont'd.)

r 2.

Primary containment integrity 2.

Integrated Leak Rate Testing shall be maintained at all times when the reactor is a.

Integrated leak rate tests critical or when the reactor (ILRT's) shall be performed water temperature is above to verify primary contain-0 212 F and fuel is in the ment integrity.

Primary reactor vessel except while containment integrity is performing "open vessel" confirmed if the leakage physics tests at power levels rate does not exceed the not to exceed 5 Mw(t).

equivalent of 0.5 percent of the primary' containment 3.

If the primary containment integ-volume per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at rity is breached when it is re-49.1 psig.

quired by 3.7.A.2, that integrity shall be reestablished within 24

b. Integrated leak rate tests hours 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 c.' the contain-ment structure that the leakage rate can be accu-rately-determined during a shorter test period, the l

agreed-upon shorter period l

may be used.

Prior to initial operation, integrated leak rate tests m'ast be performed at 49.1 l

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:

1 Lt La (L m/ Lam) 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 /> 49.1 psig.

at Amendment No.164

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Units 2 and 3 PBAPS LIMITING CONDITIONS FOR OPERATION SURVEI LLA NC E_R_E_QUIR EMENTS 3'.7.A Primary Containment (Cont'd.)

4.7.A Primary Containment (Cont'd.)

Lm

= measured ILR at 25 t

psig (Pt) l Lam

= measured ILR at 49.1 psig (Pa), and

[

Lm

< 0.7, otherwise l

i Lam (P /Pa) !

=

La Lt t

where La a 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 "peakaccidentpre.asurel Pa (psig)

Pt

= appropriately measured

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test pressures (psig) l

c. The ILRT's shall be performed at the following minimum frequency:

i 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 tthan 0.75 Lt and 0.75 La for the reduced pressure tests and peak pressure tests, respectively.

Amendment No. 164

-167-

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1 PBAPS Units 2 and 3

-I..M.ITING CONDITIONS FOR OPERATION SURVEILLANCE REODIREMENTS L

3.7.A Primary Containment (Cont'd.)

4.7.A Primary Containment (Cont'd.)

c.

Except for the initial ILRT, all ILRT's shall be performed without any pre-11minary leak detection surveys and leak repairs immediately prior to the test.

l Amendment No. 164

-168-y n7 9

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,,y Units 2 and 3 pggp3 LIMITING 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 i

accordance with Tables 3.7.2, I

3.7.3, & 3.7.4 at a pressure l

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 isolation 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 i

rate of 11.5 scf/hr for any i

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 containment is inerted, the containment shall be continucusly monitored for gross leakage by review of the-inerting system makeup requirements.

This monitoring system may be taken out of service for maintenance but shall be returned to service as soon as practicable.

l Amer;dment No. 164 169-s.-

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Units 2 and 3 PBAPS TABLE 3.~7.3 TESTABLE PENETRATIONS WITH TESTABLE BELLOWS Pen No.

Notes Pen No.

Notes N-7A Main 1 (2)(4)

N-13A RHR Pump (1(2)(4)

Steam Line 'A' 6

Discharge (6

N-7B Main (1)2)(4)

N-13B RHR Pump (6)(2)(4)

(1)

Steam Line 'B' (6)

Discharge H-7C

- Main (1)(2)(4)

N-14 Reactor Water (1)(2)(4)

Steam Line 'C' (6)

Cleanup Line

'(6)

N-70 Main (1)(2)(4)

N-16A Core Spray (1)

Steam Line 'D' (6)

Pump Discharge-(6)(2)(4)

N-9A Feedwater (1)(2)(4)

N-168 Core Spray

.(1)(2)(4)

Line 'A' (6)

Pump Discharge (6)

N-98 Feedwater (1)(2)(4)

N-17 RHR Head Spray (1)(2)(4)

Line 'B' (6)

(6)

N-11 Steam Line to (1)(2)(4)

N-201A Suppression (1)(2)(4)

HPCI Turbine (6) through Chamber to (6)

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

Cooling (6)

Pump Suction e

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' Amendment No. 16, 164

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PBAPS Units 2 and 3 LIMITING 20ND!TIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3'.7.A Primary Containment (Cont'd.)

4.7.A Primary Containment (Cont'd.)

3.

Pressure Suporession Chamber-

h. Drywell Surfaces Reactor Building Vacuum Breakers The interior surfaces of the drywell and torus shall be visually a.

Except as specified in 3.7.A.3.b inspected each operating cycle below, two pressure suppression for evidence of deterioration.

In chamber-reactor building vacuum addition, the external surfaces of breakers shall be operable at the torus below the water level all times when primary contain-shall be inspected on a routine ment integrity is required.

basis for evidence of torus The setpoint of the differential corrosion or leakage, pressure instrumentation which actuates the pressure suppression

3. Pressure Suppression Chamber-chamber-reactor building vacuum Reactor Building Vacuum Breakers breakers shall be 0.5 + 0.25 psid.
a. The pressure suppression chamber-b, From and after the date that one reactor building vacuum breakers of the pressure suppression chamber-and associated instrumentation reactor building /acuum breakers including setpoint shall be is made or found to be inoperable checked for proper operation i

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for any reason, reactor operation every refueling outage.

is permissible only during the succeeding seven days unless such

4. Drywell-Pressure Suppression vacuum breaker is sooner made opera-Chamber Vacuum Breakers l

ble provided that the repair proce-dure does not violate primary

a. Each drywell-suppression chamber containment integrity, var.cuum breaker shall be exercised through an opening-l 4.

Drywell-Pressure Suppression closing cycle once a month.

. Chamber Vacuum Breakers

b. When it is determined that a.

When primary containment is a vacuum breaker is inoperable r1guired, all drywell-suppression for opening at a time chamber vacuum breakers shall when operability is required, be operable and positioned all other operable vacuum breakers in the fully closed position shall be exercised immediately (except during testing) except and every 15 days thereafter l

as specified in 3.7.A.4.b and until the inoperable i

c below.

l vacuum breaker has been returned to normal service.

l b.

Drywell-suppression chamber vacuum breaker (s) may be

c. Once per operating cycle i

"not fully seated" as each vacuum breaker shall shown by position indication be visually inspected

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if testing confirms that the bypass area is less than or equivalent to a one-inch diameter hole.

Testing shall be initiated withing 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of initial detection of a "not fully seated" position Amendment No. 24, 127, 164

-170-

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PBAPS TABLE 3.7.2 T_ESTABLE PENETRATIONS WITH DOUBLE O-RINGS SEALS E

Pen No.

Notes N-1 Equipment (1)(2)(4)(6)

Access Hatch N-2 Equipment (1)(4)(7)(8)

+

Access and Personnel Air Lock f

N-4 Drywell Head (1)(2)(4)(6)

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

Batch N-25*

AO-2520 (Unit #2); A0-3520 (Unit #3)

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

Purge System Valves N-26 A0-2506 (Unit #2); A0-3506 (Unit #3)

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

Purge. System Valves N,35-A TIP System (1)(2)(4)(6)

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

Chamber Access Hatch l

H-205D A0-2521B (Unit #2); A0-35218.(Unit #3)

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

AO-2502A (Unit #2); A0-3502A (Unit 83)

System (1)(2)(4)(6) l l

N-205A A0-2502B (Unit #2); A0-3502B (Unit #3) Valves (1)(2)(4)[6) l N-212 Stop Check 13-9 (RCIC Stop Check)

( '. ) ( 2 ) ( 4 ) ( 6 )

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

Drain i

H-214 Stop Check 23-12 (HPCI Stop Check).

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

184-Amendment No.16,164

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PBAPS Units 2 end 3 TABLE 3.7.4 PRIMARY CONT)InMENT TESTkBLE ISOLATION VALVES

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Pen No.

Notes 7A to D A0-2-80A to D 1,2,3,4,5,9,11 a.0-2-86A 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; M0-2-33A 1,2,4,5 Check Valves 2-28A and 2-96A 1,2,4,5 9B MO-13-21; M0-2-38a; M0-12-68 1,2,4,5 Check Valves 2-28A 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 M0-23-16 1,2,4,5 A0-4807 (Unit #2) 1,2,4,5 12 M0-10-18; 1,2,4,5,9,10 M0-10-17 1,2,4,5 13A M0-10-25B; A0-10-46B; A0-10-163B 1,2,4,5 13B MO-10-25A; A0-10-46A; A0-10-163A 1,2,4,5 14 M0-12-15 (Unc r. #2) 1,2,4,5,9,10 M0-12-15 (Unit #3) 1,2,4,5,9,11 M0-12-18 1,2,4,5 16A M0-14-11B; MO-14-12B 1,2,4,5 (M0-14-12B; A0-14-13B; A0-14-15B)*

(1,2,4,5)*

16B MO-14-llA; M0-14-11B 1,2,4,5 (M0-14-12A; A0-14-13A; A0-14-15A)*

(1,2,4,5)*

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17 M0-10-32 1,2,4,5,9,10 MO-10-33 1,2,4,5 18 A0-20-82 1,2,4,5,9,11 A0-20-83 1,2,4,5-19 A0-20-94 1,2,4,5,9,11 A0-20-95 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 isolation boundary for this penetration following the' 8th Refueling Outage on Unit 3.

Amendment No. H,164

-185-

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Units 2 and 3 PBAPS TABLE 3.7.4 PRIMARY CONTAINMENT TEST 1BLE ISOLATION VALVES Pen No.

Notes 22 A0-2969A (Unit #2); A0-3969A (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 M0-2374 (Unit #2); MO-3374 (Unit #3) 1,2,4,5 25, 205B A0-2502A (Unit $2); A0-3502A (Unit #3) 1,2,4,5,9,12 A0-2505 (Unit #2); A0-3505 (Unit #3) 1,2,4,5 A0-2519 (Unit #2); A0-3519 (Unit #3) 1,2,4,5 A0-2570 (Unit #2); A0-3520 (Unit #3) 1,2,4,5,9,12 A0-2521A (Unit #2); A0-3521A (Unit #3) 1,2,4,5 A0-25218 (Unit #2); A0-3521B (Unit f3) 1,2,4,5,9,12 A0-2523 (Unit #2); A0-3523 (Unit #3) 1,2,4,5 Check Valve 9-26A; Two Check Valves 1,2,4,5 26 A0-2506 (Unit #2); A0-3506 (Unit #3) 1,2,4,5,9,12 A0-2507 (Unit #2); A0-3507 (Unit #3) 1,2,4,5 A0-2509 (Unit #2); A0-3509 (Unit #3) 1,2,4,5,9,11 A0-2510'(Unit #2); A0-3510 (Unit #3) 1,2,4,5 A0-4235 (Unit #2); A0-5235 (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 i

SV-4961B (Unit #2); SV-5961B (Unti #3) 1,2,4,5 SV-4966B (Unit #2); SV-5966B (Unit (3) 1,2,4,5 SV-8100 (Unit 82); SV-9100 (Unit #3)-

1,2,4,5 i

SV-8101 (Unit #2); SV-9101 (Pa'

'3) 1,2,4,5 i

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 1

35F SV-109; Check Valve 1,2,4,5 37A to D CRD Insert; BCD 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; BCU 18 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-f 39B M0-10-31A 1,2,4,5,9,10 l

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-Amendment No. 7'3, 90, 164

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PBAPS TABLE 3.7.4 PRIMARY CONTAINMENT TESTABLE ISOLATION VALVES Pen No.

Notes 41 A0-2-39 1,2,4,5,9,11 A0-2-40 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 SlA 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-39780 (Unit #3) 1,2,4,5 SIC 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 j

51D SV-2980 (Unit #2); SV-3980 (Unit #3) 1,2,4,5 l

Check Valve 52F A0-2969B (Unit #2); A0-3969B (Unit #3) 1,2,4,5 Check Valve l

l 53 -, -

MO-2201B (Unit-82); M0-3201B (Unit #3) 1,2,4,5 54

- M0-2200B (Unit #2); M0-3200B (Unit #3) 1,2 4,5 55 MO-2200A (Unit #2); MO-3200A (Unit #3) 1,2,4,5 56 MO-2201A (Unit #2); M0-3201A (Unit #3) 1,2,4,5 57 A0-2-316 1,2,4,5,9,11 A0-2-317 1,2,4,5 102B Breathing Air System - 2 Gate Valves (Unit #3) 1,2i4,5,9,21 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)

SV-4960D (Unit #2); SV-5960D (Unit #3).

1,2,4,5 1,2,4,5 SV-4961D (Unit #2); SV-5961c (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 Amendment No. #, 73, 90, 164

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PBAPS Units 2 and 3 TABLE 3.7.4 PRIMARY CONTAINMENT TESTABLE ISOLATION VALVES Pen No.

Notes 205A A0-2502B (Unit #2); A0-3502B (Unit #3) 1,2,4,5,9,22 Check Valve 9-26B 1,2,4,5 210A M0-10-34B 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 MD-10-38B 1,2,4,5,9,11 M0-10-33B; MD-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 M0-10-39A; MD-10-34A; Check Valve 1,2,4,5 SV-4951A (Unit #2); SV-5951A (Unit #3) 1,2,4,5

212, A0-4240 (Unit #2); A0-5240 (Unit #3) 1,2,4,5,9,11
214, A0-4241 (Unit #2); A0-5241 (Unit #3) 1,2,4,5 217B A0-4247 (Unit !?); A0-5247 (Unit #3) 1,2,4,5,9,11 A0-4248 (Unit #2); A0-5248 (Unit #3) 1,2,4,5 MO-4244 (Unit #2); M0-5244 (Unit #3) 1,2,4,5,14 MO-4244A (Unit #2); M0-5244A (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 i

21'8A A0-2968 (Unit #2); A0-3968 (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 A0-2511 (Unit #2); A0-3511 (Unit #3) 1,2,4,5,9,12 A0-2512 (Unit #2); A0-3512 (Unit #3) 1,2,4,5 A0-2513 (Unit #2); A0-3513 (Unit #3) 1,2,4,5,9,11 A0-2514 (Unit #2); A0-3514 (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 Amendment No. /#, 73, 90, 164

-187a-a w-a,-v--,

r

+-r

,e

.r,-

--ey-w t'-e,9-T---9 nr-y w

PBAPS Uni:s 2 and 3 i

TABLE

-3.7.4 PRIMARY CONTAINMEirl_ S's.3TAELE ISOLATION VALVi.S Pen No.

Notes 221 Check Valve 13-38 17 Check Valve 13-10 15 2?3 Check Valve 23-56 17 Check Valve 23-12 15 224 M0-14-26A; Check Valve 14-66A; (Unit #2) 17 Check Valve 14-66Ci 3 Check Valves (Unit #2) 17 225 M0-14-71;-M0-13 39 17 M0-13-41; M0-14-70 1,2,4,5,9 226A to D M0-10-13A to D; _RV-10-9?A to D 17 227 MO-23-57 17 MO-23-58 1,2,4,5,3 228A to D MO-14-7A to D 17 22S Check Valve 14-66B (Unit #2)

?7 2 Chud: Valves (Unit #2 only) 1.

Check Jalve 14-66D (Unit #2) l~s 230 Check Valve 13-29 17 233 M0-23-31 (Unit #2) 17 234 M0-14-26B (Unit #2) l'i 2 Check Valves (Unit #2) l'/

PASS Check Valve (Unit #2) 17 234A MD-14-26B ' Unit 3)-

17 3 Check Valves (Unit #3) 17 234B M0-14-26A (Unit #3) 17 2 Check Valves (Unit #3) 17 Pass & Check Valve (Unit #3) 17 L

235 MO-23-31 (Unit #3) 17 236A Check Valve 14-66B (Unit #3) 17 I

j Chuck Valve 14-66D (Unit #3) 17 236E Check Valve 14-66A (Unit #3) 17 4

Check Valve 14-66C (Unit #3) 17 2 Check Valves-(Unit #3) 17

~

Amendmelit No. //6, 73, 90, 164

-187b-Am

cw Units 2 and 3

~

PBAPS NOTES FOR Tt.BLES 3.7. 2 THROUGU 3.7. 4 (1)

Minimum test duration for all valves and penetrations listed is one hour.

(2)

Test pressures of at least 49.1 psig for all valves and penetrations except MS1V'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.

(-5)

Local leak tests on all testable isolation valves shall be performed each operating cycle but in no case at intervals greater than 2 years.

(6)

Local leak tests on all testable penetrations shall be performed t?"h operating cycle but in no case at intervals greater than year;s.

(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 valves are t'ested 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) times the normel force induced by test differential pressure except for valves MO-10-31A,B which is 7.97.

This applies to the following valves:

MO-2-74 M0-10-31A, B M0-13-15 MD-10-18 MO-23-15 MD-12-15 (Unit #2)

MD-10-32 (Unit #2)

Amendment No. 30, 164

-188-

.- l

Units 2 and 3 PBA?S 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 M0-12-15 (Unit #3)

A0-4240 (5240)

A0-20-94 A0-4247 (5247)

A0-2509 (3509)

M0-10-38A and B A 0 3 9 M0-10-34A and B A0-2-316 A0-20-82 A0-2513 (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 hi-directional sealing.

This applies to the following ;alves:

A0-2520 (3520)

A0-2506 (3506)

A0-2511 (3511)

A0-2521B (3521B)

A0-2502A (3502A)

(13) Manual globe valves tested in reverse direction.

'ihls applies to valves on the following penetrations:

N-32C (two valves)

N-218C (two valves)

N-32D (two valves) i These valves are locked closed except during ILRT's.

l l

(14) Gate valve utilized for containment isolationLin both directions.

Test performed only in one direction.

Valve normal force ratio is 17.9.

Leakage path is between separate torus penetrations only.

l l

Amendment No.164

-188a-

! su s PBAPS Units 2 a'.J 3.

NOTES FOR TABLES 3.7.2 THRbOGH 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) Deleted (17) hese lines discharge below the minimum torus water level and will thus have a water seal after an accident.

Therefore Type C testing of these valves is not required per Appendix J to 10 CFR 50, Section III.C.3.

A 1

Amendment No. 164

-188b-i

-N

me w

PBAPS Units 2 and 3 I

NOTES FOR TABLES 3.7.2'THkOUGH 3.7.4 (CONT'D)

(18)

Individual valves on the CRD hydraulic control units are not Typed C tested.

Leakage is tested during the Type A and 3

reactor vessel hydrostatic testing.

(19)

The TIP shear valves are 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)

Explosive valve may be tested in reverse direction.

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.

(22)

Butterfly valve tested in reverse direction.

Test acceptable since valve provides equivalent-bi-directior.al sealing.

This applies to valves A0-2502B and A0-3502B.

s I

Amendment No.164

-188c-

____.m___-._---------

l t

)

- #p* *scu9'o UNITED STATES E ~

  • m / ",%

NUCLEAR REGULAiDRY COMMISSION 5.g "f 5 WASHING TON. D. C. 20$$$

t x?

1 [,!

s9 PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELTCThTC'hhD~ BAY LDMPANY DELFARYA'PDWEW AhD'llGhT CDMPAhT~ ~

'hTihhilftlKliFCihlCCOMPANY D_0,C_KET NO. 50-278 PEACH BOTTOM, ATOMIC POWER _STA, TION, UNIT N,0.,3 i

l AMENDMENT TO FACIL11Y OPERATING LICENSE Amendment No. 167 i

License No. DPR-56 1.

The Nuclear Fegulatory Comission (the Commission) has found that:

A.

The application for amendment by Philadelphia Electric Company, et.

al. (the licensee) dateo November 18, 1976 and supplemented April 19, 1984, October 10, 1986, April 21 and June 23, 1988 and May 17, 190' complies with the standards and requirements of the Atomic Ene w nct of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter 1.

(

B.

The facility will operate in conformity with the application, the l

provisions of the Act, and the rules and regulations of the Commission; I

C.

There is reasonable assurance (i) that the activities authorized by this anendo,ent can be conducted without endangering the health and

^

safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health or safety of the public; and l

E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of i

the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical l

Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating Lic.ense No. DPR-56 is hereby amended to read as follows:

i

-2a (T)

,Te,chnical Specifications The Technical Specifications contained in Appendices A and E, as

(

revised through Amendment.No.157 are hereby incorporated in the licer.se.

PEC0 shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION hc

$Y Charles L. Miller, Director Project Directorate I-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Attachurt:

Chat.ges to the Technical l

Specifications l

l Date of Issuarce: October 23,1991 l

I I

.,. ~...... _..

ATTACWENT TO LICEySE,?pEyD[EyT,p0.,357 FACILITY OPERAllNG LICENSE NO. DPR-56 00CKE1 NO. 50-?78 Peplace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.

Remove Insert 166 166 167 167 168 168 169 169 170 170 184 184 184a 185 185 186 186 187 187 187a 187b 188 128 188a 180b 188c

_____,________z._-.__._-..--_

PBAPS Units 2 and 3 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.,7.A Primary Containment (Cont'd.)

4.7.A Primary Containment (Cont'd.)

2.

Primary containment integrity 2.

Integrated Leak Rate Testing shall be maintained at all times when the reactor is a.

Integrated leak rate tests l

critical or when the reactor (ILRT's) shall be performed water temperature is above to verify primary contain-0 212 F and fuel is in the ment integrity.

Primary reactor vessel except whil?

containment integrity is performing "open vessel" confirmed if the leakage physics tests at power levels rate does not exceed the not to exceed 5 Mw(t).

equivalent of 0.5 percent of the primary' containment 3.

If the primary containment integ-volume per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at rity is breached when it is re-49.1 psig.

quired by 3.7.A.2, that integrity shall be reestablished within 24 b.

Integrated leak rate tests hours 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 c.' the contain-ment structure that the I

leakage rate can be accu-rately determined during a shorter test period, the agreed-upon shorter period may be used..

Prior to initial operation, l

integrated leak rate tests must be performed at 49.1 i

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 L

of the following values:

I La (L m/ Lam)

Lt

=

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 /> 49.1 psig.

at Amendment No.167

-166-

r nus 2 and 3 i

PBAPS j

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS l

l 3.7.A Primary Containment (Cont'd.)

'4.7.A Primary Containment (Cont'd.)

Lm

= measured ILR at-25 t

psig (Pt) l Lam

= measured ILR at 49.1 psig (Pa), and l

Lrg

< 0.7, otherwise l

Lam l

Lt (P /Pa) !

=

La 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 Pa

= Peak accident (Psig) pressure l Pt

= appropriately measured test pressures (psig) l 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 l

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 tthan 0.75 Lt and 0.75 La for the reduced pressure tests and peak-prescure teste, respectively.

Amendment No.167

-167-W

PBAPS Units 2 and

')

MMITIMG CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS

'.7.A Primary Containment (Cont'd.)

'3.7.A Primary Containment (Cont'd.)

4

e. Except for the initial ILRT, all ILRT's shall be performed without any pre-11minary leak detection surveys and leak repairs immediately prior to the test.

l P

Amendment No. 167

-168-

nics : and 3 PBAPS LIMITING 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 testsble 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 isolation valves shall be tested at a pressure of 25 psig for leakage during each refueling outage, but in no case at intervcis 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 to correct the condition.

g.

_Centinuous Leak Rate Monitor When the primary containment is inerted, the containment stall be continuously monitored for gross leakage by review of the inerting system makeup requirements.

This monitoring system may 'e u

taken out of service for maintenance but shall be returned to service as soon as practicable.

Amendnv No. 167

-169-

PBAPS Units 2 and 3' LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE0VIREMENTS

-3.7. A Primary Containment (Cont'd.)

4.7.A Primary Containment (Cont'd.)

I 3.

P_ressure Suporession Chamber-

h. Drywell Surfaces Reactor Building Vacuum Breakers The interior surfaces of the a.

Except as specified in 3.7.A.3.b drywell and torus shall be visually inspected each operating cycle below, two pressure suppression for evidence of deterioration.

In chamber-reactor building vacuum addition, the external surfaces of breakers shall be operable at the torus below the water level all-times when primary contain-shall be inspected on a routine ment iritegrity is required.

basis for evidence of torus The setpoint of the differra corrosion or leakage, pressure instrumentation w^

actuates the pressure sup,.a

.n

3. Pressure Suppression Chamber-chamber-reactor building vacuum Reactor Building Vacuum Breakers

-breakers shall be 0.5 + 0.25 psid.

b.

From and after the date.that one

a. The pressure suppression chamber-reactor building vacuum breakers of the pressure suppression chamber-and associated' instrumentation j

reactor building vacuum breakers including setpoint shall be is made or found to be inoperable for any reason, reactor operation checked for proper operation is permissible only during the every refueling outage.

i succeeding seven days unless such

4. Drywell-Pressure Suppression vacuum breaker is sooner made opera-Chamber Vacuum Breakers ble provided that the repair proce-dure does not violate primary
a. Each drywell-suppression chamber containment integrity.

vaccuum breaker shall be 4

Drywell-Pressure Suppression exercised through an opening-

. Chamoer vacuum Breakers closing cycle once a month.

a.

When primary containment is

b. When it is determined that required.all drywell-suppression a vacuum breaker is inoperable chamber vacuum breakers shall for opening at a time be operable and positioned when operability is required, in the fully closed position all other operable vacuum breakers (except during testing) except shall1be exercised immediately and every 15 days thereafter as specified in 3.7.A.4.b and c below.

until the inoperable-vacuum breaker--has been b.

Dryweli-suppression chamber returned to normal service, vacuum breaker (s) may be

c. 0nce per operating cycle "not fully seated" as each vacuum breaker shall shown by position indication be visually inspected if testing confirms that the bypass area is less than or equivalent to a one-inch diameter hole.

Testing shall be initiated withing 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of initial detection of a "not fully seated" position Amendment No. 23, I30, 167

-170-

_____.n_.._--------

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)

Access and Personnel Air Lock f

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); A0-3520 (Unit #3)

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

Purge System Valves

~

N-26 A0-2506 (Unit #2); A0-3506 (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)

Chcmber Access Hatch N-205B A0-2521B (Unit #2); A0-3521B (Unit #3)

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

A0-2502A (Unit #2); A0-350?A (Unit #3)

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

N-205A A0-2502B (Unit (2); A0-3502B (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)

Anendment No.15,167

~104~

Uni:s 2 and 3 PBAPS TABLE 3c7.3 TESTABLE PENETRATIONS WITH TESTABLE BELLOWS Pen No.

Notes Pen No.

Notes N-7A Main (1)(2)(4)

N-13A RHR Pump (1)(2)(4)

Steam Line 'A' (6)

Discharge (6)

H-7B Main (1)2)(4)

N-138 RHR Pump (1)(2)(4)

Steam Line 'B' (6)

Discharge (6) l N-7C Main (1)(2)(4)

N-14 Reactor Water (1)(2)(4) i Steam Line 'C' (6)

Cleanup Line (6)

N-70 Main (1)(2)(4)

N-16A Core Spray (1)(2)(4)

Steam Line 'D' (6)

Pump Discharge (6)

N-9A Feedwater (1)(2)(4)

H-168 Core Spray (1)(2)(4)

Line *A' (6)

Pump Discharge (6)-

N-98 Feedwater (1)(2)(4)

N-17 RHR Head Spray (1)(2)(4)

Line 'B' (6)

(6) l H-ll Steam Line to (1)(2)(4)

N-201A Suppression (1)(2)(4)

HPCI Turbine (6) through Chamber to (6)

H-20lH Drywell Vent Line H-12 RHR Shutdown (1)(2)(4) l Cooling (6)

Pump Suction l

l l

l Amendment ko. f 3,167

-184a-

PBAPS Units 2 and 3 TABLE 3.7.4 PRIMARY CONTAINMENT TESTABLE ISOLATION VALVES Pen No.

Notes 7A to D A0-2-80A to D 1,2,3,4,5,9,11 A0-2-86A to D 1,2,3,4,5 8

M0-2-74 1,2,4,5,9,10 MO-2-77 1,2,4,5 9A MO*23-19; M0-2-38A 1,2,4,5 Check Valves 2-28A and 2-96A 1,2,4,5 98 M0-13-21; h0-2-38B; MD-12-68 1,2,4,5 Check Valves 2-28A and 2-96B 1,2,4,5 10 MO-13-15 1,2,4,5,9,10 M0-13-16 1,2,4,5 11 M0-23-15 1,2,4,5,9,10 M0-23-16 1,2,4,5 A0-4807 (Unit #2) 1,2,4,5..

12 M0-10-18; 1,2,4,5,9,10 M0-10-17 1,2,4,5 13A MD-10-25B; A0-10-46B; A0-10-163B 1,2,4,5 13B MO-10-25A; A0-10-46A; A0-10-163A 1,2,4,5 l

14 M0-12-15 (Unit #2) 1,2,4,5,9,10 M0-12-15 (Unit #3) 1,2,4,5,9,11 MO-12-18 1,2,4,5-

^

16A M0-14-llB; MO-14-12B 1,2,4,5 (M0-14-12B; AO-14-13B, A0-14-15B)*

(1,2,4,5)*

16B MO-14-llA; MO-14-11B 1,2,4,5 (M0-14-12A;-AO-14-13A; A0-14-15A)*

(1,2,4,5)*

17 MO-10-32 1,2,4,5,9,10 MO-10-33 1,2,4,5 18 A0-20-82 1,2,4,5,9,11 A0-20-83 1,2',4,5 19 A0-20-94 1,2,4,5,9,'11 A0-20-95 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 isolation boundary for this penetration following the 0

8th Refueling Outage on Unit 3.

2 I

Amendment No. 46, 740, 167 185-

,g,__

.y,

,,,w,,

.y,,w,,y

,,4

--,,--w,,,my,,,

-www,,,,we-,,,.,

,,,v

PBAPS TABLE 3.7.4

}

PRIMARY CONTAINMENT TES[ABLE ISOLATION VALVES Pen No.

Notes 22 A0-2969A (Unit #2); A0-3969A (Unit (3) 1,2,4,5 Check Valve 1,2,4,5 23 M0-2373 (Unit #2): MO-3373 (Unit #3) 1,2,4,5 24 MO-2374 (Unit #2); M0-3374 (Unit #3) 1,2,4,5 25, 205B A0-2502A (Unit #2); A0-3502A (Unit #3) 1,2,4,5,9,12 A0-2505 (Unit $2); A0-3505 (Unit #3) 1,2,4,5 A0-2519 (Unit #2); A0-3519 (Uni t #3) 1,2,4,5 A0-2520 (Unit #2); A0-3520 (Unit #3) 1,2,4,5,9,12' A0-2521A (Unit #2); A0-3521A (Unit #3) 1,2,4,5 A0-2521B (Unit #2); A0-3521B (Unit #3) 1,2,4,5,9,12 A0-2523 (Unit #2); A0-3523 (Unit #3) 1,2,4,5 Check Valve 9-26A; Two Check Valves 1,2,4,5 26 A0-2506 (Unit #2); AO-3506 (Unit #3) 1,2,4,5,9,12 A0-2507 (Unit $2); A0-3507 (Unit-#3) 1,2,4,5 A0-2509 (Unit #2); A0-3509 (Unit #3) 1,2,4,5,9,11 A0-2510 (Unit #2); A0-3510 (Unit #3) 1,2,4,5

.AO-4235 (Unit $2); A0-5235 (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-13) 1,2,4,5 SV-4960B (Unit $2); SV-5960B (Unit #3) 1,2,4,5 SV-4961B (Unit #2); SV-5961B (Unti #3) 1,2,4,5 SV-4966B (Unit #2); SV-5966B (Unit #3) 1,2,4,5 SV-8100 (Unit #2); SV-9100 (Unit #3i-1,2,4,5 SV-8101 (Unit #2); SV-9101 (Unit f3) 1,2,4,5 32C, b ILRT System Two Globe Valves 1,2,4,5,13 35A to E TIP Ball Valves 1,2,4,5 TIP Shear Valves 19 i

35F SV-109; Check Valve 1,2,4,5 i

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; DCU 18 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 M0-20-26A 1,2,4,5 SV-4949A (Unit #2); SV-5949A (Unit #3)

Check Valve

~

1,2,4,5 1,2,4,5 Amendment No. #6, 72, 90,167

-186-l

~

_., _.. _ _,. ~.,. _,., _. _. _.

.. ~.,

Cr.its 2 and 3 p

g TABLE 3.7.4 PRIMARY CONTAINMENT TESTABLE ISOLATION VALVES Pen No.

Notes 41 A0-2-39 1,2,4,5,9,11 A0-2-40 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-297GE (Unit #2); SV-3978E (Unit #3) 1,2,4,5 Sla SV-2671D (Unit #2); SV-3671D (Unit #3) 1,2,4,5 SV-2978D (Unit #2); SV-3978D (Unit #3) 1,2,4,5 5'lC 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 52F A0-2969B (Unit #2); A0-3969B (Unit #3) 1,2,4,5 Check Valve 53 MO-2201B (Unit #2); MO-3201B (Unit #3) 1,2,4,5 54

- h0-2200B (Unit #2); M0-3200B (Unit #3) 1,2,4,5 1

55 MO-2200A (Unit #2); MO-3200A (Unit #3) 1,2,4,5 56 M0-2201A (Unit #2); MO-3201A (Unit #3) 1,2,4,5 57 A0-2-316 1,2,4,5,9,11 A0-2-317

-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 43) 1,2,4,5 SV-2978B (Unit #2); SV-3978B (Unit #3) 1,2,4,5 SV-4960D (Unit #2); SV-59600 (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 Amendment No. M, 72, 90,-167

-187-O

- - - - " - - ^ ^ - - - - - -^

PBAPS Uni:s 2 and 3 TABLE 3.7.4

~

PRIMARY CONTAINMENT TESTABLE ISOLATION VALVES Pen No.

Notes 205A A0-2502B (Unit #2); A0-3502B (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 MD-10-34A 1,2,4,5,9,11 Check Valve 10-19A,C 17 211A M0-10-38B 1,2,4,5,9,11 M0-10-39B; M0-10-34B; Check valve 1,2,4,5-SV-4951B (Unit #2); SV-5551B (Unit #3) 1,2,4,5 211B M0-10-38A 1,2,4,5,9,11 MD-10-39A; M0-10-34A; Check Valve 1,2,4,5 SV-4951A (Unit #2); SV-5951A (Unit #3) 1,2,4,5

212, A0-4240 (Unit #2); A0-5240 (Unit #3) 1,2,4,5,9,11
214, A0-4241 (Unit #2); A0-5241 (Unit #3)-

1,2,4,5 217B A0-4247 (Unit #2); A0-5247 (Unit #3)

'1,2,4,5,9,11 A0-4248 (Unit #2); A0-5248 (Unit #3) 1,2,4,5 M0-4244 (Unit #2); M0-5244 (Unit #3) 1,2,4,5,14 M0-4244A (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 l

218A.

A0-2968 (Unit #2); A0-3968 (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 A0-2511 (Onit #2); A0-3511 (Unit #3) 1,2,4,5,9,12 A0-2512 (Unit #2); A0-3512 (Unit #3)

. 1,2,4,5 A0-2513 (Unit #2); A0-3513 (Unit #3) 1,2,4,5,9,11 A0-2514 (Unit #2); A0-3514-(Unit #3) 1,2,4,5 SV-2671F (Unit #2); SV-3671F (Unit #3) 1,2,4,5 t

SV-2978F (Unit-#2); SV-3978F (Unit #3) 1,2,4,5 SV-4960A (Unit #2); SV-5960A (Unit #3) 1,2,4,5 4

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 (Cnit #3) 1,2,4,5

]

Amendment No. 46, 72, 90, 167

-187a-i

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PBAPS t; nits 2 and 3 TABLE 3.7.4 PRIMARY CONTAINMENT TESTABLE ISOLATION VALVES Pen No.

Notes 221 Check Valve 13-38 17 Check Valve'13-10 15 223 Check Valve 23-56 17 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; MD-13-39 17 M0-13-41; M0-14-70 1,2,4,5,9 226A to D MD-10-13A to D; RV-10-72A to D 17 227 MO-23-57 17 MO-23-58 1,2,4,5,3 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) li 234 MO-14-26B (Unit #2) 17 2 Check Valves'(Unit #2) 17 PASS Check Valve (Unit #2) 17 234A M0-14-26B (Unit 3) 17 3 Check Valves (Unit #3)-

17 i

234B MD-14-26A (Unit #3) 17 2 Check Valves (Unit #3) 17 Pass & Check Valve (Unit #3) 17 235 MO-23-31 (Unit:#3) 17-236A Check Valve '14-56B (Unit: 83) 17 Check Valve 14-66D (Unit.f3) 17 236B Check Valve 14-66A (Unit 83).

17 Check Valve 14-66C (Unit #3) 17 2 Check Valves (Unit #3)-

17 1

AmendmentNo.h6,72,90,167

-187b-

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Dnits 2 and 3 PBAPS NOTES FOR TABLES 3. 7. 2 THRODGB 3. 7. 4 (1)

Minimum test duration for all valves and penetrations listed is one hour.

(2)

Test pressures of 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.

(5)

Local leak tests on all testable isolation valves shall be performed each operating cycle but in no case at intervals greater than 2 years.

(6)

Local leak tests on all testable penetrations shall be performed each operating cycle but in no case at intervals greater than 2 years.

(7)

Personnel Air Locks shall be tested at 6-month intervals.

(8)

The personnti air locks are tested at 49.1 psig.

(9)

Identifies isolation valves that may be tested by applying pressure be, tween the-inboard and outboard valves.

(10)

Gate valves are t'ested 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) times the normal force induced by test differential pressure except for valves MO-10-31A,B which is 7.97.

This applies to the following valves:

MO-2-74 MD-10-31A, B M0-13-15 MD-10-18 MO-23-15 MD-12-15 (Unit #2)

MO-10-32 (Unit #2)

Amendment No. 29,167

-188-

Units 2 and 3 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 M0-12-15 (Unit #3)

A0-4240 (5240)

A0-20-94 A0-4247 (5247)

A0-2509 (3509)

M0-10-38A and B A0-2-39 M0.'0-34A and B A0-2-316 A0-20-82 A0-2513 (3513)

Inner manual valve on penetration N-23.

(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:

A0-2520 (3520)

A0-2506 (3506)

A0-2511 (3511)

A0-2521B (3521B)

A0-2502A (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.

(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.

Amendment No.167

-188a-l l

l PBaps Units 2 and 3 NOTES FOR TABLES 3.7.2 THROOCH 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) releted (17) These lines discharge below the minimum torus water level and will thus have a water seal after an accident.

Therefore Type C testing of these valves is not required per Appendix J to 10 CFR 50, Section III.C.3.

i i

i Amendment No. 167-

-188b-g w

m --

-*se

  • i"Y'

PBAPS Units 2 and 3 NOTES FOR TABLES 3. 7. 2' THROUGH 3. 7. 4 (CONT'D)

(18)

Individual valves on the CRD hydraulic control utiits are not Typed C tested.

Leakage is tested during-the Type A and reactor vessel hydrostatic testing.

(19)

The fIP shear valves are 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)

Explosive valve may be tested in reverse direction.

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.

(22)

Butterfly valve tested in reverse direction.

Test acceptable since valve provides equivalent-bi-directional sealing.

This applies to valves A0-2502B and A0-3502B.

2 Amendment No.167

-188c-l l

-

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