ML20064F028
| ML20064F028 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 11/09/1978 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20064F030 | List: |
| References | |
| NUDOCS 7811270246 | |
| Download: ML20064F028 (22) | |
Text
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UNITED STATES l
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' '4 NUCLE AR REGULATORY COMMISSION 3..! hiO h
WASHINGTON, D. C. 20555 5
POWER AUTHORITY OF THE STATE OF NEW YORK DOCXET NO. 50-333 i
JAMES A. FITZPATRICK NUCLEAR POWER PLANT AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No. 40 License No. DPR-59 1.
The Nuclear Regulatory Commission (the Commission) has found that:
f A.
The application for amendment by the Power Authority of the State of New York (the licensee) dated February 23, 1976 as supplemented July 5,1978 (date j
of NRC receipt), and application dated August 1,1978, comply with the standards and requirements of the i
Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules l
and regulations of the Commission; C.
There is reasonable assurance (i) that that the activities authorized by this amendment can be conducted without endangering the healtn 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 and 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 l
all applicable requirements have been satisfied.
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f 2.
Accordingly, the license is amended by changes to the Tecnnical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-59 1s hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 40, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Tecnnical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION es Thomas A. I polito, Chief Operating Reactors Branch #3 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications 4
l Date of Issuance:
November 9,1978 l
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i kTTACHMENTTOLICENSEAMENDMENTNO.40 FACILITY OPERATING LICENSE NO. DPR-59 DOCKET NO. 50-333 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area cf change.
Remove Insert 113 113 114 114 117 117 121a 171 1 71 172 1 72 172a 174 174 175 175 199 199 200 200 201 2 01 202 202 209 209 211 211 212 21 2 213 213 e
4.5 (cont'd)
JAFNPP 5 (cent'd) u.
Flow Rote Onco /3 nontho Test - Coro spray pumps shall deliver at least 4,625 gpm against a sys-tem head cor-responding to a total pump developed head of 2113 psig l
c.
Pump Opera-Once/ month bility d.
Motor Oper-Once/ month ated Valve e.
Core Spray Header op Instrumenta-tion check Once/ day Calibrate Once/3 months Test Once/3 months f.
Logic system once/each Functional operating Test cycle
/
g.
Testable Tested for check valves operability any time thy reactor is ir the cold con-dition e x c e e f. -
l ing 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, l
if operability I
tests have not been performed during the pre-ceding 31 days.
113' I
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From and after the dato that 2.
I en it is determinod that one one of the core Spray Systemo Core Spray System in inoperablo is made or found inoperable for the operable core Spray System, any reason, continued reactor the LPCI System, and the emergency operation is permissible during diesel generators shall be the succeeding 7 days unless demonstrated to be operable the system is made operable immediately.
The remaining earlier, provided that during Core Spray System shall be the 7 days all active demonstrated to be operable components of the other Core daily thereafter.
Spray System and the LPCI System and the emergency diesel generators shall be operable.
t l.
The LPCI mode of the RHR System 3.
LPCI System testing shall be as shall be operable whenever ir-specified in 4.5.A.1.a, b,
c, radiated fuel is in the reactor d,
f and g except that three RHR and prior to reactor startup pumps shall deliver at least from a cold condition, except 23,100 gpm against a system as specified below.
head corresponding to a reactor vessel pressure of 20 psig.
a.
From the time that one of the RHR pumps is made or a.
When it is determined that found to be inoperable for one of the RHR pumps is any reason, continued inoperable, the remaining 1
reactor operation is per-active components of the missible during the LPCI, containment spray succeeding 7 days unless subsystem, both Core Spray the pump is maae operable Syctems, and the emergency earlier provided that diesel generators required during such 7 days the for operation shall be remaining active demonstrated to be oper-components of the LPCI, able immediately, and the l
containment spray mode, remaining RHR pumps shall all active components of be demonstrated to be a
both Core Spray Systems, operable daily thereafter.
and the emergency diesel generators are operable.
114
}4; 40 Amendment No.
e A
4.
Should one of the containment cooling syboyotoco becomo in-operable, continued. reactor operation is permissible for a period not to exceed 7 days, unless such subsystem is sooner made operable provided that during such 7 days all active components of the other containment cooling sybsystem, including its associated diesel generator, are operable.
5.
If the requirements of 3.5.B cannot be met, the reactor shall be placed in a cold condition within 24 hr.
6.
Low power physics testing and reactor operator training shall be permitted with reactor 0
coolant temperature 4212 P with an inoperable component (s) as specified in 3.5.B above.
2.
High Pressure Coolant Injection C.
High Pressure Coolant Injection (HPCI) _ System (HPCI) System j
1.
The HPCI System shall be oper-Surveillance of HPCI System able whenever the reactor pres-shall be performed as follows sure is greater than 150 psig provided a reactor steam supply and irradiated fuel is in the is available.
If steam is not reactor vessel and prior to available at the time the reactor startup from a cold surveillance test is scheduled condition, except as specified to be performed, the test shall below:
be performed within ten days of continuous operation from the time steam becomes available.
1.
HPCI System testing shall be as specified in 4.5.A.l.a,b, l
c, d,
f, and g except that the HPCI pump shall deliver at least 4,250 gpm against a system head corresponding to j
a reactor vessel pressure of 117 1,120 pnic to 159 pnic.
l, j
3.5 (cont'd)
JAFNPP 4.5 (cont'd)
E.
Rosctor Core IRolation Cooling E.
Reactor Core Icelation Cooling (RCIC) Systen (RCIC) System 1.
The RCIC System shall be oper-1.
RCIC System testing shall be able whenever there is irradi-performed as follows provided ated fuel in the reactor vessel a reactor steam supply is and the reactor pressure is available.
If steam is not greater than 150 psig and prior available at the time the to a reactor startup from a surveillance test is scheduled cold condition, except from the to be performed, the test shall time that the RCIC System is be performed within ten days made or found to be inoperable of continuous operation from for any reason, continued the time steam becomes available reactor power operation is permissible during the suc-Item Frequency ceeding 7 days unless the system is made operable earlier a.
Simulated once/ operating provided that during these 7 Automatic cycle days the HPCI System is Actuation operable.
Test 2.
If the requirements of 3.5.E b.
Pump Oper-Once/ month cannot be met, the reactor ability shall be placed in the cold condition and pressure less c.
Motor Oper-Once/ month than 150 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ated valve Operability 3.
I.o w power physics testing and reactor operator training shall d.
Flow Rate Once/3 months be permitted with inoperable components as specifled in e.
Testable Tested for 3.5.E.2 above, provided that Check Valves operability i
reactor coolant temperature is any time the 4 2120F,
reactor is in the cold condi tion exceeding 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, if operability tests have not been performed during the pre-coding 31 days 121 f
wa
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a r'. JAFNPP 4.5 (cont'd) 3.5 (cont'd)
The RCIC pucp chall delivor at least 400 gpm for a system head corresponding to a reactor pressure of 1,120 psig to 150 psig.
2.
When it is deterAined that the RCIC System is anoperable at a time when it Ja required to be operable, the IIPCI system shall be demonstreted to be operable immediately and daily thereafter.
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JAFNPP 4.7 (cont'd) c.
Type C tests (1.) Type C tests shall be performed by local 1
pressurization.
The pressure shall be applied in the same direction as that when the valve would be required to perform its satety function, except as listed in Table 3.7-1 unless it can be l
determined that the results from the tests for a pressure applied in a different direction will provide equivalent
'i or more conservative results.
Each valve to be tested shall be closed by normal operation and without any preliminary
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exercising or adjustments.
(2.) valves,
unless pressurized with fluid from a
seal system, shall be pressurized with air or nitrogen at a pressure of Fa, and the gas flow to maintain Pa shall be measured.
(3.) valves, which are sealed with fluid from a seal
- system, such as the liquid in the suppression chamber shall not be tested.
171
JAFNPP 4 7 (cont'd) e (4.) S2e tablo 3.7-2 for exceptions.
(5.) Acceptance criterion -
The combined leakage rate for all N netrations and valves subject to Type B and C tests shall be less than 0.60 La.
Leakage from containment isoletion valves that are sealed with iluid from a sea 1 system may be excluded when determining the combined leakage rate provided that the installed isolation valve seal-water system fluid inventory is sufficient to assure the sealing function for at least 30 days.
d.
Other leak rate tests (1) The leakage rate for containment isolation valves 10-A0V-68A, B (penetration X-13A,B) for Low Pressure Coolant Injection System and 14-A0V-13A,B (penetration X-16A,3) for Core Spray.
System shall be less than 11 cubic feet per minute per valve (pneumatically tested at 45 psig with ambient temperature) or 10 gallons per minute per Y ' "t*'I' I Y} *"O O
172 at 1000 psig with ambient temperature.
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JAFNPP 4.7 (cont'd)
Periodic rGtGst Echedule.
l e.
(1.) Type A test.
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.
4 172a
/. 7 (cont'd)
The third test of each set shall be conducted when the plant is shut down for the 10 -year plant inservice inspections.
Permissible periods for testing.
The performance of Type A tests shall be limited to periods when the plant facility is nonoperational and secured in the shutdown condition under the administrative control and in accordance with the plant safety proced ures.
(2.) Type B tests.
Type B
- tests, (except tests for air locks),
shall be performed during each reactor shutdown for refueling, or other convenient intervals, but in no case at intervals greater than 2. years.
Air locks shall be tested at 6-month intervals. However, air locks which are opened and closed during such intervals shall be tested within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> except when primary containment integrity is not required.
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JAFNPF 4.7 (c:nt'd) ^
(3.) Type C test.
Type C tests shall be performed during each reactor shutdown for refueling but in no case at intervals greater than two years.
(4) Other leak rate tests specified in Section 4.7d shall be performed during each reactor shutdown for refueling but in no case at inter-vals greater than two years, f.
Containment modification Any major modification, replacement of a component which is part of the primary reactor containment
- boundary, or resealing a
seal-welded door, performed after the preoperational 1eakage rate test shall be followed by either a Type A, Type B, or Type C
- test, as applicable, for the area affected by the modification.
The measured leakage from this test shall be included in the test report.
The acceptance criteria as appropriate, shall be met.
Minor modifications, replacements, or resealing on seal-welded
- doors, performed directly prior to the conduct of a
scheduled Type A test do not 174 require a separate test.
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J M t.F P TABLL 3.7-1 toont 'd)
PROCT.SS P2 Pttitin, Pt.18tTbATitU Pkth7JtY (titeTA1.Jttt?r (l.uhrs an p.n enthemes are ke yeu to msabers on f ollowisN pages; signal codes are listeu on followans, pages.)
Power locat ion Swer Clusirve Drvwell Valve typ=
t o ups t.
a.c f. t o to Close Isolation 1mc taormal Rem.rk. ano a,a ne !=olate d h ne tration (6) 153 16) Group _Drywell J1 f 6)
S l yn.,1_
E_
St.tus Exceptions 1
..an t pbro.- to h-31Ac Check Procase C
Outside Psocess bev. flow t:ot arp-Open e sa,.
A-3 tac litable
.ec t a c s
44ha o.ur..
to h-JtAc ths ek Process C
Inside Pr oce s a Rev. ilma hot agp-oper.
r ec a t e g am ip A-3 t t.c 1*1 cable i.eu me.ttua h-12 fu Cate De A
Outsade De A,U,F,hn 3u see Closed t.l.uteowie CC,ol-ans surply
. win s=cactor 1-12 50 Cate Ac A
Inside Ac A,U, t, Id1 38 see Llosed aht:tuuwn cool-a ne. sus,s.ly Mr tu autpres-A-211A,B MO Clobe Ac uut s tee Ac C.S,5Je 10 see Closed Throttlinal type store s g.a.a f valve Note (2) s.t.oer s.e:A - contaan-X-39A,b FU Cate Ac 9
Outenue Ac G,S.RM 10 see Closed Note (2) sent sg.s ay c.tk - cont ain-E-J y s., b NO Gate Ac h
outside Ac C.S.FM 10 see Closed taote (2) sa. nt spr.y idth - reactor h-17 HD Gate Ac A
Inside Ac A.U, F, pet 20 see closed w.u sp. ray cJim - ae.etor 4-17 FEJ Cate De A
tsutside De A U,F,PM 20 see Closed I.e.u s pr.e y
.oin to surpres-R-210A,b fu Clobe Ac h
Outside Ac G,RM 70 see closed Tttrottling type ston xel valve - Note (2) e 3l Nt,e - LFCI to x-11A,b 90 Cate Ac A
outside Ac FM.H 120 see Closed se.ctor hMR - !.,PCI to X-13A,a lo Globe Ac A
outside a an, n 90 see open Thrott11ag type 3l reactor valve - Note (10)
Mim - LFCI to R-13A,8 Au Check A
Inside Process Rev. flow Not app-Closed Testable check a
reactor 11 cable valve ( 3,16)
I 199
kl1ri1N TABt.E 3.7-1 (Cont'd)
^
m PROCESS PIPELINE PENETRATINC PRIMARY CONTAI5HENT_
signal codes are listed on following pages.)
(Numbers in parentheses are keyed to numbers on following pagest Power Location Power Closing Drywell Valve Type to Open Ref. to to Close Isolation Time Normal Remarks and
- 1. ins Irelated Penetration (6)
(5) _(6)
Croup Drywell_
(5) (6)
_Slanal g_
Status Exceptions Rl!R pump suc-X-225A,8 MO Cate Ac 8
Out, side Ac RM Not appli-Open cable tion from sup-praesica pool A
Outside Procese Rev. flow Not appli-Closed Stendby liquid X-42 Check cable centrol A
Inside Process Rev. flow Not appli-Closed Setndby liquid X-42 Check cable control Racetor water X-14
'HO Cate Ac, A
Inside Ac A.J,RM 30 sec Open cleanup from rsector Ratetcr water X-14 M0 Cate De A
outside De A.V,J.RM 30 sec Open cleanup from rateter Ratcror water X-14 Ho Cate De A
outside De A.V,Y,J.RM
- 10 see Closed frem reactor varm-up A
Outside Process Rev. flow Not appli-Open Rzector water X-9A check cable clatnup return Ac X,RM 15 sec Open) Opens on Sig B:
RCIC - turbine X-10 HO Cate Ac A
Inside
) line break Sig K stsca supply
) overrides to RCIC - turbine X-10 H0 Cete De A
outside Dc K,RM 15 see open).close valves steas supply Closed RCIC - turbine X-212 Check Fwd. flow B
Outside Process Rev. flow cxhrust RCIC - cinimum X-210A M0 Clobe Dc B
Outside De K,RM 5 see Closed pu=p flow RCIC - pump X-9A MO Cate De 8
Outside Dc RM Not appli-Closed cable di: charge 200
,R JAFNPP TABLE 3.7-1 f0ont'on PROCESS P1PELIFE PEldETWATItC PkIMAPY LOtrTAIWLIFF fles.bers in p rentt. eses are keyea to numbers on f ollowing pagest signal codes are lasted on following pages.)
Power Location Power Closing Urywell valve Type to Open I<et. to to Close Isolation Time terrul Remarks and 1.an.* Isolatud len. trat ton f65 f 5116) Group Drywell 151 f 61 Sign al (7)
Status Except&ons Wil, to radw.ste X-2JSA Du Gate Ac B
Outside Ac A, F, RF.
24 see Closed luta to z.awaste X-225A PD Gate Dc o
outside Dc A,F,RM 24 sec Closed SCIC - v.cussa X-226 Check ned. flow (
Outside Process i ev. f low -
Closed paap diset.arge 1
,GC - g up x-224 MO Gate Dc h
Outside Dc EM Not app-Closed duettor.
licable 8
Outside Dc RM Not app-Closed gCIC 6uw X-224 ap Gate Dc a.uctions licable Core spray -
X-210a,b MO Gate Ac h
Outside Ac RM Not app-Closed utatsaus pap licable slone thzw spr.y to X-16A,b MO Gate AC A
Outside Ac RM Isot app-Open swactor 11 cable Lore spray to X-lea,3 MO Gate Ac A
Outsiae Ac SM Mot app-Closed reactor licable Lbre spray to X-16 A,8
, Jd) Check (3)
A Inside leote (3)
Rev. taow hot app-Closed Testable check licable valve - moto (3,16) l r..ctor,
thre spray test X-210A,k FD Globe Ac D
Outside Ac G,RM 45 see Closed to supprwasion tool Corm spray pu g X-227A,ne tu Gate Ac 5
Outside Ac RM Not app-Open suction licable Drywell equip-X-19 P:0 Plug Ac Inside Ac A,F,RM 30 sec Open sent dr.in sump aascrwrge urywell equip-X-19 Ao plug Air /ac 3
Qutside Spring A, F,RM Hot app-Open usnt drain sump 11 cable atschegge 201 4
JAPNPP A
.m TABt.E 3.7-1 (Cont'd)
PROCESS PIPELINE PENETRATINC PRIMARY CONTA1FINT (Numbers in parentheses are keyed to numbers on following pages: signal codes are listed on following pages.)
Power 1.ocation Power Closing Dryvell Valse Type to Open Ref. to to Close Isolation Time Nor al Remarks and Line Isolated Penetration (6) f5) (6)
Croup Drvwell.
(5) (6)
Signal (7)
Status Exceptions Dryvell floor X-18 NO Plug Ac 5
Inside Ac A.P.RM 30 sec open drain su=p discharge Drywell floor X-18 A0 Plug Air /Ac 5
Outside Spring A,P,RM Not appli-Open drain su=p dis-cable charge Traveling in-X-35A,B C.D Explosive De A
outside De RM Not appli-Open One valve on each line cera probe shear cable Treveling in-X-35A B C.D SO Ball Ac A
Outside Ac A.P.RM Not appli-Open One valve on each line cora probe cable Note (14)
Traveling in-X-358 Check Pvd. flow A
Outside Process Rev. flow Not app 11-Closed core probe purge cable a
HPCI - turbine X-11 P0 Cate Ac A
Inside Ac L.RM 20 sec Open ) Signal "C epens stste supply
) valve. Signal **L
) overrides and
) closes valve.
HPCI - turbine X-11 MO Cate De A
Outside De L,RM 20 see closed) etsam supply EPCI - turbine
.X-214 Check Pvd. flow B
Outside Process Rev. flow Not app 11-Open Closes on rev. flow crA:ust cable or low exhaust pressure.
HFCI - turbine X-214 Check Pwd. flow B
Outside Process Rev. flow Not appli-Open exhrust cable ILPCI Pu:2p X-226 NO Cste De B
Outside Dc L RM 60 see Closed auction l
MFCI - pu=p X-95 M0 Cate De B
Outside De RM Not app 11-Closed discharge cable HFCI - turbine X-222 Stop Check Pvd. flow 5
Outside Process Rev.'f1'ow Not appli-Closed exhtust drain cable HPCI - cinicun X-2105 Check Pwd. flow B
'Outside Process Rev. flow Not appli-Closed pu p flow cable 202
JAFNPP 1rCTES FOR TABLE 3.7-1 (CONT'D) 9.
Coincident low reactor water level signal "G" and low reactor pressure signal "T"
open LPCI
- valves, except that recirculation line break signal *R" overrides to close LPCI valves on borken side and automatically opens the LPCI valves
-in the opposite loop.
Special interlocks permit testing these valves with manual switch during any mode of reactor operation except when coincident signals "G" and "r? are present.
10.
Coincident signals "G"
and "T"
open valves.
Special interlocks permit testing these valves by manual switch except when au,tomatic signals are present.
11.
Normal status position of valve (open or closed) is the
(
position during normal power operation of the reactor (see " Normal Status" colu:an).
12.
The specified. closure rates are as required for containment isolation only.
es 13.
Minimum closing time is based on valve and line size.
o 14.
Signal "A"
or "F"
causes automatic withdrawal of TIP t
probe.
When probe is withdrawn, the valve automatically closes by niechanical action.
15.
Reactor building ventilation exhaust high radiation signal "Z"
is generated by two trip units.
This required one unit at high trip or both units at down scale (instrument f ailure) trip, in order to initiate
(
isolation.
16.
Leak testing shall be accomplished in accordance with section 4.7.A.2.d.
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JAFNPP TABLE 3.7-2 l
EXCE.PTION 'FO TYPE C TESTS Certain Type C tests will be performed or omitteG as follows:
Penetration System valve J_ scal 14ak Rate Test Performed X-7A, B, C, Main Steam 29-AUV-80A,~B,
'these valves are air-operated globe valves -
and D C, and D pressurized in reverse direction and meas-29-A0v-86A B,
urement of lesakage will be equivalent to C, and D results from pressure applied in the same direction as when the valves umsid be required to perform its saf ety f unction.
Therefore, pressure will be applied between the isolation valves and leakage measured.
A water seat of 25 psag will be used on the intnard valve to determine the out* nard valve's leak rate.
(limit 11.5 scita at f
25 psig)
X-10 RCIC 13-Mov-15 See 1-25 (27-AOV-131A, B)
X-11 ffPCI 23-MOV-15 See X-25 (27-A0V-131A, B)
X-25 Dry well Inerting 27-ADV-112 This. valve is a butterfly valve - pressur-CAD and Purge ization in reverse direction and measure-ment of leakage will be equivalent to results from pressure applied in the same direction as that when the valw would be required to perform its satety function.
X-25 Dry Well Inerting 27-A0V-1314
'these valves will be tested in the reverse CAD and Purge 27-AoV-1318 direction, since the system was not de-signed for pressure to be applied in the same direction as that when the valve I
would be required to perform its safety functlon.
Basis - The pressurization direction was
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not a requirement at tie time of plant designs to redesign the system to permit this is not feasible as it would delay plant operation.
X-26 JVB Dry Well Inerting 27-AOV-113 See X-25 (27-Aov-112)
CAD and Purge 27-MOV-113 This globe valve will be tested in the reverse direction. See X-25 (27-AOV-131A, 8) 211
JAFNFP g
l TABI. 3.7-2 ccorreDi h tr.ation System Valve local Isak Rate Test Performed 27-SOV-120B See X-2% (27-A0V-131A, B) 17-SOV-1213 27-SOV-1225 k-31 Bd Dry well Inerting 27-SOV-125B See X-25 (27-A0V-131A)
CAD and Purge X-39A Cont. Spray 10-F.oV-31 A Mis valve will be pressurized in the reverse direction and leakage measured.
See X-25 (2 7-SOV-131 A, 9)
X-398 Cont. Spray 10-MOV-31A See X-39A X-45 ILRT VSP.-100T See X-25 (27-A0V-131 A, B)
X-59 Dry Well Inerting 27-Sov-123A See X-25 (27-AoV-131A, B)
Cad and Purge X-202 Torus Vacuum ADV-101A/B See X-25 (27-A0V-112)
Breakers X-203A Dry Well Inerting 27-SOV-1198 Se e I-25 (27-A0V-131A, B)
CAD and Purge X-203B Dry Well Inerting 27-SOV-124A See X-25 (27-ADV-131 A)
CAD and Purge 1-205 Dry well Inerting 27-A0V-117 See X-25 (27-A0V-112)
CAD and Purge 27-MOV-117 See I-25 (27-MOV-113)
X-210 A/B RCIC, RHR Will not be tested as lines are water sealed by suppression chasiber water See X-25 (27-A0V-131A, B)
X-211A RNR 10-MOV-38A
. h is valve will be tested in the reverse direction. See X-25 (27-ADV-131A, B) 1-2113 RHR 10-puV-388 This valve will be tested in the reverse direction.
X-212 RCIC 13-MOV-130 See X-25 (27-Auv-131A/B)
X-218 II.RT VSM-100T See X-25 (27-AUV-131 Afd)
X-220 Dry Well Inerting 27-A0v-116 See X-25 (27-A0V-112)
CAD and Purge 27-50V-132A See X-25 (27-A0V-131A/B) 27-Sov-1323 X-222 MPCI See X-210 A/B X-224 RHR See X-210 A/B X-225 RHR See X-210 A/B i
{
212 i
r-n JAFMPP l
ranz.e 3.7-2 scowr.m Penetration Systene Valve Incal leak Rate Test Perforwd 1-226 ifPCI See X-210 A/B X-227 Core Spray See X-210 A/S X-228 Condensate See X-210 A/B 9
en 9
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0 213
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