ML20203E437
| ML20203E437 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 02/12/1997 |
| From: | Pierno T SOUTHERN CALIFORNIA EDISON CO. |
| To: | |
| Shared Package | |
| ML19317C790 | List:
|
| References | |
| SO23-XVII-3.1.1, NUDOCS 9712170062 | |
| Download: ML20203E437 (22) | |
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Reclear fraleing Olet:1st. A!MS Caeretsster. t.50 lite lechnical Services Ottisten Tes N/A k les N/A PAGE 1 0F 4 -
o NUCLEAR ORGANIZATION SITE TECHNICAL SERVICES PROCEDURE S023-XVII-3.1.1 UNITS 2 AND 3 REVISION 2 PAGE 1 0F 18 EFFECTIVE DATE 1ER I 21997 AEFUEl1NG OUTAGE INTERVAL EXAMINATION Of THE RfACTOR CO0lANT PRESSURE BOUNDARY 10 OETECT LEAKAGE JABLEOFCONTENTS T
$ECTION f. AGE 1.0 OBJECT!YES 2
2.0 REFERENCES
2 3.0 PREREQUISITES 3 4.0 PRECAUTIONS 3' 5.0 CHECKLIST 3 6.0 PROCEDURE 4 7.0 RECORDS 5 ATTACHMENTS 1 Components Subject to Visual Examination (VT-2) 16 Under Examination Category B-P and B-E 2 Test Sumary Report of (VT-2) Categories B-P and B-E 17 3 VT-2 System Pressure Test Report 18 RECENEDCDM FEB 121997
- XVil311.W61 QA PROGRAM AFFECTING SITERLECOPY
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NUCLEAR ORGANIZATION SITE TECHNICAL SERVICES PROCEDURE 5023-Xyllo301.1 ;
UNITS 2 AND 3 REVISION 2 PAGE 2 0F 18 i i
REFUEllNGOUTAG{J((RVALEXAMINATION QF THE REACTOR COOLANT PRE 550Kt BOUNDARY TO DETECT LEAKAGE 1.0 OBJECTIVES 1.1 To define the requirements and boundaries for examinations performed to detect leakages in the Reactor Coolant System.
1.2 To assure compliance with the Technical Specifications referenced in Section 2.1.
1.3 To meet the requirements of the applicable regulations, and Codes referenced in Section 2.1 to the maximum extent practicable.
2.0 REFERENCES
2.1 NRC Comitments 2.1.1 American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, " Rules for the Inservice Inspection of Nuclear Power Plant Components",1989 Edition, no Addenda 2.1.2 Title 10. CFR, " Energy",Part 50, " Domestic Licensing :,f Production and Utilization Facilities", Chapter 55a, "Codesar.dStandards"(10CFR50.55a) 2.1.3 Units 2 and 3 Technical Specification 5.3.2.10 g 2.1.4 Units 2 and 3 LCS 5.0.103.2.5 2.1.5 FinalSafetyAnalysisReport(FSAR)Section3.2,
" Classification of Structures Components and Systems" 2.1.6 Topical Quality Assurance Manual (TQAM) Section 7E,
" Inservice Inspection" 2.1,7 Federal Register, Vol. 57, No.152, August 6,1992, Rules and Regulations 2.2 Q.thtt 2.2.1 FormSCEEG(123)7,VT-2SystemPressureTestReport
l r10 CLEAR ORGANIZATION SITE TECHNICAL SERVICES PROCEDURE 5023 XYll-3.1.1 UNITS 2 AND 3 REVISION 2 PAGE 3 0F 18 3.0 PRERE0VISITES 3.1 Before using this document, verifr the revision and any issued TCNs 1 and/orECs(EditorialCorrections;)arecurrentbyusingoneofthe following methods: {
3.1.1 AccesstheNuclearDocumentManagementSystem(NDMS)
(preferedmethod).
3.1.2 Check it against a Corporate Documentation Hanagement-SONGS (COMSONGS) cont-olledcopyandany issuedTCNs/ECs.
3.1.3 Contact CDM-50NG5 by telephone or through counter inquiry.
3.1.4 Obtain a user-controlled copy of this procedure from COM-SONGS or NDMS.
3.2 Only persons certified to at least level II VT-2 shall perforrr or witness examinations under this procedure. Level !! VT-2 personnel certification is required under Subarticle IWA-2300 of Reference 2.1.1.
3.3 Prior to performirm examinations required under this procedure, the examiner shall verify that the Reactor Coolant System is at a nominal q operating pressure corres>onding to 100% rated reactor power (0 2250 psia). The temperature 51all be greater than or equal to 280*F.
3.3.1 If Code Case N-498 is invoked in lieu of hydrostatic testing, a 4-hour hold time is required for insulated systems.
3.3.2 for systems borated for the purpose of controlling reactivity, insulation shall be removed from pressure retaining bolted connections for visual examination VT-2.
4.0 PRFCAU' IONS 4.1 To maintain radiation exposures As low As Reasonably Achievable (ALARA)performallworkinconformancewiththere established on the Radiation Exposure Permit (REP) quirementsfor the job.
4.2 Observe extreme caution to avoid burns or contamination when working around any components that have had their insulation removed for visual examination.
5.0 CHECKLIST 5.1 Attachment 1 to this procedure lists all components in the Reactor Coolant Pressure Boundary subject to examination.
NUCLEAR ORGANIZAi!0N
$1TE TECHNICAL SERVICES PROCEDURE S023-XVII-3.1.1
. UNITS 2 AND 3 REVISION 2 PAGE 4 Of 18 6.0 fjl0CEDURE 6.1 Resnonsibility 6.1.1 TheInserviceInspectionEngineer(ISIEngineer),who !
reports to the Supervisor. lSI and Erosion <
responsible for the performance of the exam / Corrosion, is inations required under this procedure.
6.2 Component Description :
6.2.1 Components classified as 'C0de Class 1" in accordance with Reference 2.1.5, and which are subject to reactor lk operating pressure and temperature under conditions equivalent to 100% Reactor Power, require examination under this procedure. These components are listed in Attachment 1.
6.2.2 The components subject to examination under this ;
3rocedure make up Examination Category B P and B E of (eference 2.1.1. t 6.3 Examination HQIh Ite'ns on Attachment 1 marked with an "" are items i
withpressureretainingboltingrequiring) examinationforboricacidperIWA-5242(a (see visual Step 3.3.2).
6.3.1 Conduct visual examination for evidence of component pressure-boundary leakages, structural distress, or corrosion prior to returning the unit to service following a refueling outage, (for other than controlled or .
collected leakages).
6.3.2 Performtheexamination(whichmaybeconductedwithout the removal of insulation except as noted in 3.3.2) by inspecting the exposed surfaces and joints of ccaponent 3 insulation to locate evidence of leakage. Examine the floor areas, or equipment directly underneath components, ,
for evidence of leakage which may have come from above.
6.3.3 Conduct an examination of insulation joints along vertical !
surfaces of vessels, walls, and piping galy if the ~
following condition is ng.t met:
.1- The lowest terminal ends of vertical surfaces are
. examined, and the insulation design is such that any leakage originating above can drain from the insulation joint at its lowest elevation.
6.3.4: Identify and record the source and quantity of any leakage :
originating from gaskets, valve stem seals or packing, or- !
. pump seal packages. The P".S Cognizant Engineer shall review this data prior to returning the plant to service.
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l NUCLEAR ORGAHlZATION SITE TECHNICAL SERVICES PROCEDURE 5023-XVII-3.1.1 UNIT 5 2 AND 3 REVISION 2 f
i PAGE 5 Of 18 6.4 Documentation 6.4.1 Examine each component listed in the areas on Attachment 1. If the examination was completed in a satisfactory manner, initial and date on the corresponding signoff line.
6.4.2 Document the results of the examinations on Attachment 3 (VT-2SystemPressureTestReport).
6.4.3 Components not found, components inaccessible due to plant or radiological conditions, or new components not yet documented in the procedure shall be documented on the Test Sunniary Report section of Attachment 2.
6.5 Acceptance Criteria 6.5.1 Leakage originating from welds or through wall leakage from any pressure retaining component are unacceptable and require corrective action prior to returning the unit to service.
.1 Conduct re-examination in accordance with Section 6.3, following repains or replacements of components covered under this procedure, 7.0 f1Cp_R01 7.1 Prepare and maintain records and reports of inservice inspections as required by Reference 2.1.1.
7.2 Submit original documents and data reports to CDM-SONGS within 90 days of their completion. COM-SONGS shall maintain the original documents for the operational life of the plant.
7.2.1 Maintain Inservice Inspection Files for a minimum of five years.
IMPierno:XVil311.W61
HUCLEAR ORGANIZATION SITE TECHNICAL SERVICES PROCEDURE S023-XV!1-3.1.1 UNITS 2 AND 3 REVISION 2 PAGE 6 0F 18 l
ATTACHMENT 1 COMPONENTS SUBJLCT TO VISUAL FXAMINATION (VT-2)
UNDER EXAMINATION CATEG0P1 8-P AND B-E AREA IA - 17' INSIDE BIOSHIELD E-089 SIDE Description Corponent P&TD Verified Sv/Date Hot Leg 1201-001-42"-A 40111A(S03) /
Hot Leg 40111A(503)
Sampling System 1201-023-3/(4"-A3/4" root) 1201MU006 /
Hot Leg 1201-018-%"-A" 40111A(503) n DLHS !solations 1201MUO29 N 1201MU001 /
Refueling LI 1201-028-2"-A 40111A(S03) 1201MU007 4" 1201MUO46 4" /
Hot Leg Injection 1204-147-3"-A 40111A(503)
- 1204MU152 (3" check) 1204-165-3"-A 1204MR169f3/4" vent) 1204MR231 I 3/4" vent) 1204MR168 I 1" drain) 1204MR237 I 1" drain) 1204MR048 I,34" vent) 1204MR228 i,3 4' vent) __
/
P001 Crossover Leg 1201-003-30"-A 40111A(503) /
P001 Crossover 1201-019-2"-A 40111A(503)
Drafn to RCOT 1201MU026 1201MU002
/
P001 Cold Leg 1201-007-30"-A 40111A(503) /
PZR Spray Line 1201-011-4"-A 401110(503) from P001 CL 1201-011-3"-A 1201MR213(vent) 1201MR214 (vent)
- 1201MU972 /
- - Boric Acid Examination ATTACHMENT 1 PAGE 1 0F 11
NUCLEAR ORGANIZATION SITE TECHNICAL SERVICES PROCEDURE 5023-XVII-3.1.1 UNITS 2 AND 3 REVISION 2 PAGE 7 Of 18 ATTACHMENT 1 COMPONfHTS SUBJECT TO VISUAL EXAMINATION (VT-2)
UNDER EXAMINATION CATEGORY B-P AND B-E (Continued)
AREA IA - 17' INSIDE BIOSHIELD E-089 SIDE (Cor.tinued) pf,5cription Component Ellg Verified By/Date PZR Spray Line
- PV-0100A 40111D(503) from P001 CL 1201MR220 (Continued) 1201MR219 1201-012-1'-A 1201HUO42 1201MU982 f")
1201MU983
- 1201MU976
- check) 1201MR218 1201MR217 1201-206-l'-A 1201MU984 f "
1201MU985 J"
- 1201MU973d* /
Pressurizer 1201-060-2'-A 40123A(503)
Aux Spray 1201HUO19 2" check) 1201MR032 l' drain 1201MR067 l' drain /
Charging to P001 1201-062-2"-A-FE0 40123A(503)
Cold Leg 1201MUO21 2' check) 1201MR068 l' drain 1201MR033 1* drain /
P003 Crossover Leg 1201-005-30"-A 40111A(503) /
P003 Crossover Drain 1201 021-2"-A 40111A(503) to RCDT and Letdown 1201MUO27(2')
1204HU004 (2")
1201-022-2"-A
- 1201MU991 (2") 40123A(S03)
- TV-0221 1201-059-3/(4"-A3/4")
1201MU110
- HV-9204 /
P003 Cold Leg 1201-009-30'-A 40111A(503) /
- - Boric Acid Examination ATTACHMENT 1 PAGE 2 0F 11 l
NUCLEAR ORGAN!ZATION SITE TECHNICAL SERYlCES PROCEDt'RE 5023-XVII-3,1,1 UNITS 2 AND 3 REVISION 2 PAGE 8 0F 18 ATTACHMENT 1 COMPONE3TS SUllJECT TO VISUAL fxAMINATION (VT-2) lLNJER EXAMINATION CATEGORY B-P ANQ_jL-f, (Continued)
AREA 18 - 17' IN5f0E BIOSHIFt0 E-088 SIDE Description Coroonent Egg Verified 8v/Date Hot Leg 1201-002 42"-A 40111A(S03) /
Hot Leg Sampling 1201-065-3/4"-A 40111A($03) 1201HUO34(3/4") /
SDC fron Hot Leg 1201-016-16" A 401120(503) to 51 1201-016-18"-A 1201MR066 1" drain 1201MR004 1" drain /
P002 Crossover Leg 12014006-30"-A 40111A(503) /
P002 Crossover Drain 1201-031-2"-A 40111A(503)
To RCDT 1201MUO25 -
1201MU005
/
P002 Cold Leg 1201-010-30*-A 40111A(503) /
P004 Crossover Leg 1201-004-30"-A 40111A(503) / ._,
P004 Crossover Drain 1201-020-2" A 40111A(503) to RCOT 1201MUO24 1201MU003 /
P004 Cold Leg 1201-008-30"-A 40111A(503) /
AREA II - 17' OUTSIDE BIO 5HIEtD Hot Leg Injection 1201-072-3"-A 401120(503)
Loop 2 *1204MU156(3" check) 1204-167-3 -A
' 1204MUO67 1204MUO32 3"))
3f4*
- 1204HU158 3 check) 1204MR204 3/4" root) 40112C($03) 1204-168-1"-A
- HV-9433 /
- - Bo.ic Acid Examination AF ACHMENT 1 PAGE 3 Of 11 L.
NUCLEAR ORGAHilATION SITE TECHNICAL SERVICES PROCEDURE 5023 XYll-3.1.1 UNITS 2 AND 3 REVISION 2 PAGE 9 0F 18 ATTACHMENT 1
[@_PA'{flli_311!UECT TO VISUAL EXAMINAT10N (Yl-21 UNDER EXAMINATION CATEGORY B-P AND B.E (Continued)
AREA II - 17' OUTSIDE B10$ HIE 10 (Continued)
Description Component fjJp, Verified 8v/Date Hot leg Injection 1204-166-1'-A 401120(503)
Loop 1
- HV 9437 1204 165 3" A 1204MR293([4' 1204MUO66 i vent)
)
- 1204MU157 ") 40112C($03) 1204MUO3') i(3/4')
d 1201-126-2 -A 40123A(503) 1201MR172 l' drain 1201MR171 1" drain /
SDC from Hot Leg 1201-016-18* A 40112D(503) to 51 1201-016-16*-A
- HV-9377
- HV-9339
- PSV-9338 1201MUO35 3 1201-055-3/(4*-A1201-072-10'/4"
- HV-9378
-A-FE0 drain)
- PSV 9363
- HV-9337 1201-051-3/(4'3/4* drain) 1201MUO48 /
AREA I!! - 30' PENETRATION OUTSIDE 810$HIELD Charging 1201-061-2" A 40123A($03)
- HV-9202 1201-062-2" A
- HV-9203 1201MR072(3/4"veat) 1201HR073(3/4" vent) 1201-063-2" A
- 1201MU107 (2")
1201-056-2'-A
- XCV-9219 /
- - Boric Acid Examination 1
ATTACHMENT 1 PAGE 4 0F 11
NUCLEAR ORGANIZATION SITE TECHNICAL SERVICES PROCEDURE $023oXVII 3.1.1 UNITS 2 AND 3 REVISION 2 PAGE 10 0F 18 ATTACHMENT 1 COMP 00INTS SUjKCT TO VISUAL EXAMINATION (VT-2)
U1 DER EKAMINATION CATEGORY B-P AND B-E (Continued)
AREA 111 - 30' PENETRATION OUTSIDE BIO 5NIELD (Continued)
Descristion Component M. Vertfled tv/ bate Aux Spray Bypass 1201-126-2'-A 40123A(503)
(Pen 68) *1201MU128(2')
1201MU133 (3f4') /
- 1201MU129 L2 check)
Pressurizer Aux 1201 060-2'-A- 40123A(503)
Spray
- HV-9201 1201MR074 3 4' vent 1201MR075 3 4' vent /
Si to Loop 1A *1204MUO72(8' check) 401120(503)
(Pen 48) 1204 043 8'-A 1204MR241(Drainl 1204MR185 1204-152-3{0
.A rain)40112C(503)
- 1204MU018(3* check) 1204MR037(Vent) 1204MR227-(Vent) 1204-043 4' A 1204MR047 1204MR239 1204MR017(3/4" root) 40113A(503) /
Si to Loop 1B 1204-044-8"-A 401120(503)
(Pen 49) *1204MUO73(8' check) 1204 153-3"-A 40112C(503)
- 1204MU019(3' 1204MR018(3/4' root check))
40113A(503) /
- - Soric Acid Examination i
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NUCLEAR ORGANIZATION $1TE TECHNICAL SERYlCES PROCEDURE 5023. XVII 3.1.1 UNITS 2 AND 3 REVISION 2 PAGE 11 Of 18 ATTACMMENT 1 COMPONENTS SUBJECT T0 VISUAL EXAMINATION (VT-2)
UNDER EXAMINATION CATEGORY B P AND B-E (Continued)
AREA !!! - 30' PENETRATION OUTSIDE BIOSHIELD f(qqtjgtjj, Description Component f.llR Verified Iv/Date 51 to Loop 2A 120%.045 8'-A 40112D(503) i (Pen 50) 1204MUO74ll8' check) 1204MR218 1,0 rain) 1204MR246 i 1204MR240 (,1"Drain) drain) ,
1204MR179 i l' drain) ,
1204MR233 q,3/4" vent 1204MR183 i ,3/4' Vent))
1204-154-30-A 40112C($03) 1204MUO20(3" 1204MR019(3/4' root check))
40113B(503) /
SI to Loop 28 1204-046 8"-A 40112D(503)
(Pen 51) 1204MUO75 ll8' check) 1204MR042 i, Drain 1204MR264 1, Drain 1204MR256 I Drain 1204MUO21(3*chec) 40112C(S03) 1204-155-3"-A 1204MR020 (3/4' root) 401138(503) /
AREA IV'- 30' IN510E IIOSHIELD Safety injection 1204-043-12"-A 4n113A(503) to P001 Cold Leg
- 1204MUO27 12")
1204MR317 4" vent 1204MR318 4' vent /
Safety Injection 1204-044-12"-A 40113A(503) to P003 Cold L0g
- 1204MUO29 12' check 1204MR319 3 4" vent 1204MR320 3 4' vent / e
- - Boric Acid Examination 5
ATTACHMENT 1 PAGE 6 0F 11
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NUCLEAR ORGAN!7Ai!0N SITE TECHNICAL SERYlCES PROCENRE $023 XVII-3.1.1 !
UNITS 2 AND 3 REVISION 2 PAGE 12 0F 18 ATTACHMENT 1 ,
i
[0NPOND TS SUBJECT TO VISUAL EXAMINATIOS (VT-2) t;ND [R EXAMINATION CATEGORY B-P AND 3-E (Continued)-
- AREA IV - 30' INSIDE Bt0SNIELD (Continued) j Rticrintion Compentet fl[A Verified Bv/Date-Safetyinjection 1204-046-12" A 401138(S03) to P002 Cold Leg
- 1204MUO33 I 12" check [
1204MR253 i ;34" vent 1204MR263ll34" vent /
Safety injection. 1204 045-12"-A 401138(503) to P004 Cold Leg *1204MUO31(12' check) 1204MR289 h 4' vent) 1204MR290 i , 4' vent) 1204MR180 1 4" vent) 1204MR232 L 4' vent) ./
Charging to P004 1201-061-2" A FE0 40123A(503) 1201MUO20(2" check) 1201MR147 I 1201MR148(,34" 3 4" vent)vent) /
AREA Y - 45' INSIDE 5101RIELD PZR Surge Line 1201-015-12"-A 40111B(503) 1201-049-3/4"-A 1201MUO12(3/4" root)
- FO-0118 /
PZR Spray Line 1201 013-4"-A 401110(503) from P003 Olsch 1201-013 3"-A
- 1201MU974(4*) /
- - Boric Acid Examination ATTACHMENT 1 PAGE 7 0F 11
f NUCLEAR ORGANIZATION $1TE TECHNICAL SERVICES PROCEDURE $023 ?.'lll-3.1.1 i UNITS 2 AND 3 REVISION 2 PAGE 13 0F 18 ATTACHMENT 1 }
{0MPONENTS SUBJECT TO VISUAL EXAMINATION (VT-2)
UNDER IXAMINATION CATEGORY B P AND B-E (Continued) ,
AREA V - 45' INSItt RIO5NIELD (Continued) l Descristion Consonen fM2 Verified Bv/DQ !
PZR Spray Line
- PV-01008 40111D(503) from P003 Disch 1201-014-1" A (Continued) 1201MUO43 1201MU978(q/4' ) needle) i 1201MU979 i ") :
1201MR221 (/4' vent) ,
1201MR222 ( '4' f vent) !
- 1201M'J977 check) i 1201MR215 ((34' vent) 1201MR216 L3 4' vent?
1201-205-1*-
1201MU981(1")
1201MU980 (1")
1201-014-4'-A
- 1201MU975(4') /
Comon Pzr Spray 1201-012 4'-A 401118(503) /
AREA VI - 45' OUTSIDE BIOSHIELD Loop 18 Safety 1204-056-12'-C 40113A(503)
Injection (SIT T007) 1204-072-2"-C
- HV 9352
- 1204HUO41 12' check) 1204MR248 34' vent) 1204MR247 34* vent) 1204-060-12" A
- HV9350 1204-064-1"-A
- HV9351 /
- - Boric Acid Examination ATTACHMENT 1 PAGE 8 0F 11
NUCLEAR ORGANIZATION SITE TECHNICAL SERYlCES PROCEDURE $023-XVII-301.1 UNITS 2 AND 3 REVISION 2 PAGE 14 0F 18 ATTACHMENT 1 COMPONINTS SUBJLC LTO VISUAL EXAMINATION (VT-2)
MQ.ER EXAMINATipN CATEGORY B-P AND B-E (Continued)
AREA VI - 45' OUTSIDE BIOSHIEt0 (Continued) l Description Cneponent P&TD Verified Bv/Dalp_
Loop 1A Safety 1204-055-12"-C 40113A(503)
Injection (Sli T008) 1204-071-2 -C
- HV 9342
- 1204MUO40 12" check) 1204MR139 3/4' vent) 1204MR229 3/4* vent)
- HV9340 1204-063 1"-A
- HV9341 /
Loop 2A Safety 1204-057-12*-C 40113B(503)
Injection (SIT 1009) 1204-073-2'-C
- HV-9362 I
12" check)
- 1204HUO42(3/4' 1204MR348 i vent) 1204MR347(3/4" vent)
I 1204-061 12"-A i
- HV9360 1204-065-1*-A
- HV9361 /
Loop 24 Safety 1204-058 12'-C 40113B(S03)
Injection (SIT 1010) 1204-074-2 -C
- HV-9372
- 1204MUO43 12' check) 1204MR269 3/4' vent) 1204MR270 3/4' vent) 1204-062-12"-A
- HV9370 1204-066-1"-A
- HV9371 /
- - Boric Acid Examination ATTACINENT 1 PAGE 9 0F 11
NUCLEAR ORGANIZA110N SITE TECHNICAL SERVICES PROCEDURE $023-1)!!-3,1,1 UNITS ? AND 3 REVISION 2 PAGE 15 0F 18 MTACHMENT 1 COMPOND TS $UBJECT TO VlilLALLGdlNATION (VT-2) !
IlNDER EXAMINAfl0N CATEGORY B P AND B-E (Continued)
AREA VII - 85' PRES $URIZER [
t Descrintion Component 2))) Vertfled By/ rate !
P2R Safety Valve 1201-032 6" A 40111B(503) j Piping
- PSV-0201 1201-033-6*-A PSV-0200 1201-034-3/4-A" 1201HUO11 i 1 i 1201MUO47 0 h 1201 MOO 10d )
- F0-0119 / ,
AREA VIII - TANK $. PkE550RE VE5SELS AND MISC i i
Reactor Pressure V-001 40111A(503) /
Vessel Reactor Pressure
- CEDMS/GRAYLOKS/N072LES 40111A(503) / h Vessel Head P
- Steam Generator #1
- 1201ME089 /
40141A(503)
(Primary)
- 1201ME088 40141A(503) /
(Primary)
Pressurizer
- 1201ME087 40111B(503) / ;
(includingheaters andinstrumentnozzles)
Reactor Coolant RCP1A(1201MP001) 40130A(503) /
Pumps (RCPs)
RCPIB(1201MP003) 40130B($03) / ^
RCP2A(1201MP004) 40130C(S03) /
RCP28(1201MP002) 40130D(503) /
- Boric Acid Examination ATTACHMENT 1 PAGE 10 0F 11
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.--_ _ _ . . _ . _ _ .- . - _ _ _ . _ . _ _ _ _ . _ _ . . m - _. . _ . _ __ . -
NUCLEAR ORGANIZATION SITE TECHNICAL SERVICES PROCEDURE 5023. XVII-3.1.1 UNIT 3 2 AND 3 REVISION 2 PAGE 16 0F 18 ATTACHMENT 1 COMPONDTS SUBMCT TO VISUAL EKAMINATION (VT-2)
JND ER EXAMINATION CATEGORY 1.P AND B.E - (Continued)
ARIA VIII - TANK $. PRES $URE VE11ELS AND MISC (Continued)
Descrintion Consonent fMR Verified Bv/ Sate -
Safety injection 1204MT007 40113A(503) /
Tanks and associated ,
Class 2 piping 1204MT008 / j 1204MT009 40113B($03) / .
1204MT010 / l SampiingSystem(P4) 1212ML167 to MU294 40111A($03) / '
-(P4)-1212MLO30toMU295 / ;
(P1) 1212MLO36 to MV293 40111B(503) /
(P12)1212MLO42toMU296 / !
Rx-Vessel Leak
- 1201MLO73 to HV-9418 40111A($03) /
Leak Detect Lines RxYesselHeadVent*1201MLO96toHV-296A/B 40111A(503)
/ +
- 120lMLO30 to 1201MLO96 / ,
PZR Vent Line *1201MLO94soHV.297A/B 40111B(503) / i
- 1201MLO97 to 40111C(503)
HV-298/299/M0119 /
- - Boric Acid Examination i,
.XYll311.W61 ATTACHMENT 1 PAGE 11 0F 11~
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NUCLEAR ORGAN!!ATION $1TE TECHNICAL SERY!CES PROCEDURE S023-XVII-3.1.1 UNITS 2 AND 3 REVI510N 2 PAGE 17 0F 18 ATTACHMENT 2 4
j TEST SumARY REPORT Of (VT-2) CATEGORIES B-P AND B.E i UNIT I i
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NUCLEAR ORGANIZATION SITE TECHNICAL SERVICES PROCEDURE $023.XYll.3.1.1 UNITS 2 AND 3 REVISION 2 PAGE 18 0F 18 AT1ACHMENT 3 VT.2 $YSTEM PRES}. PRE TEST REPORT
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NUMBER OF OVERSIZE PAGES FILMED ON APERTURE CAR 0(S)
ACCESSION NUMBERS OF OVERSIZE PAGES:
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