ML20126J802
| ML20126J802 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 04/21/1981 |
| From: | Bradham O, Monroe J, Shawn Smith SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | |
| Shared Package | |
| ML20126J785 | List: |
| References | |
| AP-014, AP-14, NUDOCS 8105050304 | |
| Download: ML20126J802 (156) | |
Text
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.l L];/~' SOUTH CAROLINA ELECTRIC AND GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION
, NUCLEAR OPERATIONS ADMINISTRATIVE PROCEDURE AP-014 -
PRESERVICE INSPECTION l
,, REVISION 5 APRIL 16,1981 1
O- s^zzTr azr^rzo - Reviewed by: (N & Ib fl OR IINATOR (of this re&ision) Date - - Y) s - k/ GROUP SUPERVISOR Dat e' Approved: fl l An V/A/// PLANT MANAGER /' Dat'e/] !! ll h Date Issued:
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Fo rm 'AP-101 -3, (1/80)
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- l. 4/1 6/81 ,
LIST OF EFFECTIVE PAGES 1 PAGE REVISION l. e i 5 1 5 2 5 : 3 5 i 4 5 ; 5 5 6 ' 5 7- 5 l e 5 ; 9 5 ! i r , i
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.AP-014 PAGE 1 REVISION 5 4/16/81 ,
1.0 . PURPOSE 1.1 The' purpose.of this procedure is to provide the administrative j guidelines, coordination control and the interface with associated. organizations for Nuclear Operations personnel in the i administration of. the, preservice inspection program required by , the A.S.M.E. code, section XI, for the . Virgil C. Summer Nuclear ; Station.
2.0 REFERENCES
AND GLOSSARY 2.1 References. l
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2.1.1 A.S.M.E. code, . Section XI, 1974 edition through Summer 1975 addenda. . 2.1.2 SCE&G Operational' Quality Assurance Plan. ; 2.1 3 SCE&G Quality Assurance Plan. 2.1.4- SCE&G Production Engineering Procedures.: 2.1 5 SCE&G Quality Control Procedures. (]) 2.1.6 D.C.C. Quality Control Procedures. , 2.1 7 D.C.C. Work Procedures. j _2.1.8 'SCE&G Nuclear Operations Start-Up Procedures. . j 2.1 9 VCS Administrative Procedure AP-101. l 2.1.10 Code of Federal Regulations, Title 10, Part 50 55 a(s) l
'(4).- l 2.1.11 AP-002, Qualifications of External Personnel. -
i 2.1.12 AP-1200, Inspection of Activities Affecting Quality. l l 2.2 Glossary ! 2.2.1 Abbreviations l ANII - Authorized Nuclear Inservice Inspector ! (Section 5 9 2) ! CWR - Construction Work Request; Outlined in l Start-Up Manual SUM-B-5 l l (2) - l
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AP-014
.? AGE =2 .
t REVISION 5 4/16/81 j N'CN -. Non-conformance Notice; Outlined in'AP-209 [ Nonconformance Control ; i SFR - -Start-Up. Field Report; Outlined in Start-Up Manual SUM-B-13 j
- 2.2.2 Definitions j i
Code. . in .this procedure shall refer ' to ASME Code, Section XI. j Designee. .Any individual, approved by the Manager, V. C. Summer Station or appropriate supervisor, designated to i assume the responsibilities and duties of titled plant j personnel and function in their stead, to include the , authority.to make decisions in.the same. capacity.as the ; titled plant personnel for whom assigned individual is an alternate. j c ! 30 RESPONSIBILITY l 31 The SCE&G Operations Manager, VC Summer Nuclear Station, is f responsible for the overall implementation of the preservice l inspection. program for Nuclear Operations. t The SCE&G Nuclear Operations Maintenance Supervisor is assigned ., l f] 3 2 ' the. responsibility for the coordination of scheduling
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activities, procedure development and control, problem i resolution, and the general day to day work activities ! associated with the conduct of the preservice inspection ; program. ! i! 33 SCE&G Nuclear Operations personnel are responsible for assuring ! that work'is performed in accordance with this procedure. ! 4.0 GENERAL ; t 41 ASME Boiler and Pressure Vessel Code Section XI, Rules for j Inservice Inspection.which includes preservice inspection, ! is addressed.to provide rules for the~ examination, testing, and ; inspection of Class 1, 2, and 3 components and systems in a ,i nuclear power plant. Application of this Section of the Code ;; begins when the requirements of Section III of the code, Rules - *! for Construction of Nuclear Power Plant Components,' have been l} satisfied. .jj i: i! O )l O - 1 i' l l!,) l 1
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i 4 AP-014- I
, PAGE 3 .
i REVISION 5 *
' 4/16/81 A
k / 4.2 ASME Code,:.'Section.XI, assigns SCE&G the responsibility of' j
' developing a program which will demonstrats conformance to the requirements of Section XI of the Code. The responsibilities !
~ includes. ;
- a. The. requirementsto provide access in the design and ;
arrangement of the plant to conduct the examination and tests.
- b. -Developing plans and schedules _ including detailed . l examination.and testing procedures-for filing with the enforcement and regulatory authorities having jurisdiction at1the plant site. ,
- c. Conduct of the program of examinations and test, system ;
leakageland hydrostatic pressure tests, as well'as : performance. tests of, pumps and valves.
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- d. Recording'the resu1'ts of the examinations and tests, including corrective: actions required and the actions taken, ,
4;3 Westinghouse has the responsibility of providing. access, in the , design and arrangement of the plant to conduct the required examinations and tests for Class 1 and Class 2 and GAI for Class O - 4.4' On site inspections and responsible organizations are listed , below: v e
- TYPES OF INSPECTION RESPONSIBLE ORGANIZATION a) Examination & Inspection Westinghouse (Note 1) l IWB-2000, IWC-2000 ;
b) Examination & Inspection SCE&G Nuclear Operations IWD-2000 c) System Leakage and Hydrostatic i Pressure Tests - IWB-5000, ! IWC-5000, IWD-5000 SCE&G Nuclear Operations d) Inservice Testing'of Pumps SCE&G Nuclear Operations Subsection IWP' ' e) Inservice Testing of Valves SCE&G Nuclear Operations > Subsection IWV , 4 f) . Component Supports SCE&G Nuclear Operations
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.i AP-014- ,
PAGE 4 . REVISION 5 : l E 4/16/81
) NOTE 1 --Conduct of examinations other than hydrostatic testing
. required by ASME Code, Section III, for Code Class 1 '
- and 2 systems will be performed by Westinghouse. 1 4 5' Control ~and. Interface. t In.conductin'g the on-site inspections,' testings, problem i identification and resolution, - documentation, etc. , Nuclear
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Operations end other interfacing-organizations will perform' work to.various procedures. These interfacing procedures are as
-follows:
,4 5 1 -Westinghouse Procedures. l A. ISI-QP-6.1 -
" Isometric Sketch, Preparation and l Control" . - -
B. ISI-QP-6.2 "Contrd1 of~0nsite' Inspection l Activities". ,_ j C. ISI Visual Examination Procedure. ,. l D. ISI Preservice and Inservice Examination Manual U1 transonic Equipment Qualification. ; E. ISI Liquid Penetrant Examination Procedure,., [{} ,! F. ISI Ultrasonic Examination of Studs, Bolts and Nuts. s G. ISI-17 1 " Preparation of Inspection Program
'l Reporta"s -
H. ISI Menual Ultrasonic Testing of Reactor Coolant Pump Flywheels, j I. ISI-47'- Manual Ultrasonic Examination of ; Circumferential and Longitudinal Butt Welds'in Ferritic Vessels if 2 1/2" Thick and Greater. J. ISI-52 " Operation Procedure for Reactor Vessel I! Examination Using the Westinghouse Remote Inspection Tool". ,: h' K. ISI-70, " Magnetic Particle Examination"* ! ei L. ISI-71 -
" Wet Magnetic Particle Inspection". .l !
3: M. LISI-205 - Manual Ultrasonic Examination of Full l Penetration Circumferential and Longitudinal Butt ;' Welds. , m I a, .. . . . , , , .. . . ..
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. AP-014 )
PAGE 5 i REVISION 5-
- 4/16/81 l b; " I N. OPS-NSD-101'- Preservice and Inservice. Inspection' l ;
Documentation.
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'4 5.2 SCE&G Production Engineering Procedure NE-127, ASME Code l
. Section XI, Engineering Interface Procedure.
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'4 5 3 SCE&G Nuclear Operations Procedures from the Start-Up j Manual: ';
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j A. SUM-B Construction Work Requests. , B. ' SUM-B Start-Up Field Report (SFR).- l
- . . 1 C.
. SUM-C Hydrostatic and Pneumatic Tests. j D. Surveil'1ance Testing Procedures. .
f4 5 4 SCE&G" Quality Control Procedures. , 5 I A. FQCP 2.1 4 - Nonconformance Control and Procedure. , 455 DCC Procedures. ! A. Daniel AP-VI-02','ASME Code Related - Nonconformance r3 and Corrective Action. < y o. : B. DCC- QC Procedures - Weld Inspection or Evaluation. l 4.6 Function,a1 Organization.. ' 4.6.1 A group will be established; under_the. administration of } the SCE&G Nuclear Operations Maintenance Supervisor, j to coordinate the day to day on site activities of the .; preservice inspection program. These activities include !! scheduling, procedure review, approval, revision and )! control, coordinating on site inspections, problem
- i j resolution and tracking, collecting and reviewing i results, interface with NRC and Authorized Inspection i Agency and the submittal of required documents. j 50 PROCEDURE i
5.1 -Work. Coordination. i O - 1a il 3
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a AP-014
. PAGE o
, REVISION 5 ; I.g3 4/16/81 1 k/ 5 1.1 The.SCE&G Nuclear Operations Maintenance Supe'rvisor or f his designee sh'all coordinate the day to day activities required to implement and. perform the onsite preservice !
. . inspection program. He shall call upon Nuclear .
Operations personnel and other SCE&G Organizations to ;
' assist him in performing this work. Periodically, he l shall hold meetings to update all interfacing i organizations and perform the functions set forth in this !
procedure. ; 52 Scheduling. 5 2.1 The SCE&G Maintenance Supervisor or his designee shall; I a.' Develop a schedule of inspection and' work activities. and update the schedule'as required.
- b. Ensure that interfacing organizations review the j schedule and perform work under their , interfacing ;
procedures, as required, to meet the schedule.
- c. Coordinate the work of interfacing organization and ,
that of Nuclear Operations from a schedule standpoint. ' (]) d. Keep the SCE&G Manager, V. C. Summer Nuclear Station l.' informed of the progress of the schedule and of any problems that arise in order that appropriate levels e of management may be informed. v . .; 5 3 ~ Procedure Review and Approval. 531 Subcontractor procedures used for conduction of . spections, correction of deficiencies and documentation of results shall be subjected to an administrative / technical review and approval as described L in reference 2.1 9 Work performed by these procedures will be under the guidelines of the SCE&G Operational i i Quality Assurance Plan. A " Release to Work" will be given by QA prior to the performance of any inspections by contract personnel. ; r 54 Performance of Inspection. , 5.4.1 The required inspections are listed in Section 4 4, l components to be inspected are listed in the applicable section of the preservice. plan. Performance of these : inspections- shall be in accordance with the approved j
. procedures listed in Section 4 5 by responsible organizations. Qualifications of personnel performing i f- there inspections will be in accordance with reference ,
(_g / 2.1.11 and 2.1.12. . l i
1 AP-014- : PAGE 7 l' REVISION 5 4/16/81 ; (_) 5 5 ' Technical Problem Resolution and Tracking. 551 . Technical problems discovered during the course of-the ;
, inspection will be reported'to the SCE&G Nuclear .i Operations. Maintenance Supervisor or his designee. He will decide upon the. correct. course of action to resolve the problem. Approved: site procedures such as N.C.N. 's, ,
SFR's,1CWR's, etc.,'will be used to correct these l .
. problems. Resolution of problems outside the scopeoof !
existing procedures shall be directed to appropriate ,
-levels of management or other organizations as :
appropriate. j 552 The resolution of problems may involve repairs of welds, ' components, supports, equipment, etc. Where the i requirements of ASME Code, Section III, Rules for ! Construction of Nuclear Power Plant Components, have been j satisfied and r.e. pair is necessary, repair procedures ; shall be in accordance with ASME Code, Section XI, i article IWA-4000. Where the above requirements have not ! been satisfied, repair procedures shall be in accordance ; with ASME Code, Section III. All repairs performed in j accordance with ASME. Code Section XI will be under the 1 jurisdiction of the SCE&G Manager, Quality Control and/or i SCE&G Nuclear Operations Quality Control. . ( 553 The SCE&G Nuclear Operations Maintenance Supervisor'shall establish a system for tracking problems that develop i during the preservice inspection program. The system i shill consist of appropriate log sheets or tracking forms : that will identify the problem, follow its resolution, ! and follow any required retest or inspection to close out i the problem. j D 5.6 Evaluation of Results. i i 5 6.1 The SCE&G Nuclear Operations Maintenance Supervisor or .i his designee will be responsible for ensuring that , I interfacing organizations or other qualified personnel ! perform evaluations of examinations in accordance with ! ASME Code, Section XI. Standards for evaluation of ! examination results are listed below: ) AREA 0F EXAMINATION STANDARD FOR EVALUATION' f
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- 1. Weld Examination Evaluation IWA-3000 ;
- 2. Pressure Test Evaluations IWA-5000 3 Ptun) Performance Test Evaluations IWP-3000 1
() 4. Valve Testing Evaluations .IWV-3000 I q
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AP-014
. PAGE 8 , ' ~
REVISION 5 q 4/16/81
'/ - 5 6.2 Evaluations of indications on Code _ Class 1 and 2 systems and components to determine acceptability or rejection to the requirements of ASME Code, Section XI shall be
, performed by Westinghouse through on SNT-TC-1A qualified i Level III examiner.
- a. Gilbert Associates resident enginee~r shall review the
' Westinghouse evaluation for Class 1 and 2 systems and -
components and provide disposition for any necessary action. 5 6.3 Evaluations of indications on Code Class 3 systems and components shall be eval ~uated by Gilbert Associates and the resident engineer shall provide disposition.. 5 6.4 - Evaluations conducted by other organizations shall be coordinated by the Maintenance Supervisor. ; 5.7 Qualifications of Inspection Personnel. <- L 5.7 1 All personnel performing non-destructive examination of, ' systems or components will be qualified under the i requirements of SNT-TC-1A 1975 Ed. A list of I qualifications of contractor sup'QA for review insubmitted to SCE&G/QC and SC .. () 7s accordance with Section 11 5 of the SCE&G Operationel Quality Assurance Plan and reference 2.1.11. , 58 Reports an,d w Records
~5.8.1 The SCE&G Manager, V.C. Summer Nuclear Station, shall be responsible for the compilation of results, records and inspection reports. Requirements of ASME Code, Section -
XI, Article IWA-6000 will be met. The precise formats < for recording of results are shown in the procedures listed in Section 4 5.1 and 4.5.3 5.8.2 The SCE&G Manager, V.C. Summer Nuclear Station or his designee shall be responsible for ensuring that all l: records of preservice inspection results, problem evaluation and resolution and changes to the inspection ' program are prepared and retained in accordance with the guidelines established by articles IWA-6000, IWP-6000 and IWV-6000 of the Code. , n 5.8.3 A copy of inspection, test and examination records shall be retained for the service lifetime of the component (s) l !. inspected. h 5 8.4 The SCE&G Manager, V.C. Summer Nuclear Station, will gx ensure that a preservice inspection report is prepared i (_) and submitted in accordance with the guidelines ' Author 13@d a gggggggggg gggfg}e ffhrfkhh. f the Code. 59 7 1 esse an a we en e me w e e e - es, me ** - *e +6 .< *ma es==- *e e.*=***e-. - = ,e
AP-014 PAGE 9 REVISION 5 r) 4/16/81 V 591 The Authorized Inspection Agency for preservice inspection is the American Motorists Insurance Company, a subsidiary of the Kemper Insurance Company.
.5 9 2 Duties of the Authorized Nuclear Inservice Inspector (ANII)' include witnessing any pressure testing, reviewing '
nondestructive examination procedures, reviewing repair programs, verifying that the visual examinations and test on pumps and valves have been completed and the results recorded, and requiring requalification of any welder, inspection or procedure when he has reason to believe the. requirements of the Code, are not being met. 593 The SCE&G Nuclear Operations Maintenance Supervisor will ensure that the ANII is provided with the following: A. Procedures for examination, testing, evaluation and repair of code class 1, 2, and 3 systems and components, including pumps and valves. l B. Results and evaluations of examinations of pumps and v alves . C. Schedules pertinent to the pressure testing of (- v) systems and components. - D. Qualification of personnel performing test inspection or repairs per the Code. , 594 The'SCE&G Nuclear Operations Maintenance Supervi'sor shall act as liason between the ANII and other interfacing organizations. 5 10 NRC Interface. j 1 5.10.1 The SCE&G Manager, V.C. Summer Nuclear Station or his
- designee shall be responsible for providing the NRC with !'
any information pertinent to the preservice inspection. .: He shall ensure that all records and reports are l correctly assembled, and reviewed prior to submittal to the NRC for review. The SCE&G Manager, V.C. Summer Nuclear Station or his designee shall act as the station liason for any NRC inspection or audit during the performance of the preservice inspection. l: 5 11 Revision to the scope of the Preservice Inspection Program i si 5.11.1 Changes to the number or types of components or I equipment to be inspected will be the responsibility of the organization performing the inspection. Justification for deletion, alternate means of I (~) '- inspection or additional components to be inspected will i be provided in accordance with the Code. l i i _ _ _ _ . _ . _ _.... _ _. . . . . . _, j
et l h - 1 (3 kLo 1.0 NON-DESTRUCTIVE TESTING FOR PRESERVICE INSPECTION AND
. TESTING PROGRAM
. 1 The scope of non-destructive ~ testing for preservice inspection 1.1 has been concluded at Virgil C. Summer Nuclear Station. All examinations were conducted to the extent required by Section i XI of~the ASME Boiler and Pressure Vessel Code 1974 Edition with a11' addenda through Summer 1975. Known relief from ASME Code Section XI requirements are included in request'for relief section of this part'of the Preservice Inspection Plan, j When a specific code requirement cannot be accomplished during- l actual Preservice Inspection these relief. requests will be i submitted for approval to the NRC. l 1.2 Where possible,_all welds are UT examined from both sides of the weld in accordance with ASME Code, Section V (T-535). Where welds can be examined from one side only, essentially 100% of.
the weld is examined assrcing the entire volume of the weld has been examined. 1
- f. '1. . Some of the' arrangements and details of the piping system , 1 gjll and components were designed and fabricated before the access and examination requirements of Section XI-of the i
1971 Code could be applied; consequently, some examinations are limited or not practical due to geometric configuration o or accessibility. Generally, these limitations. exist at all fitting to fitting ' joints, such as elbow to tee, elbow to valve, reducer to valve, etc., where geometry and some-times surface condition preclude ultrasonic coupling or access for the required scan length. 2.. The limitations exist to a lesser degree at pipe to fitting . . assemblies, particularly where the weld is not ground flush j with the pipe O.D. surface. At these joints, examinations , can be conducted from the pf.pe side, however, the fitting, again, limits or precludes examination from the opposite ; side. ' 4 m B-3 (Rev. 2) j: I _~.__._.___.__.
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- 3. When the weld surface is flat, the fitting side examination is replaced by a calibrated straight beam examination on the weld.
- 4. In most cases, examinations in these areas were accomplished as a besc effort attempt to cover as much of the required area (generally, the weld and base metal for 1 "T" on each side) as possible, however, the extent of examination coverage in the base metal of the fitting or component cannot be specifically qualified.
- 5. . Areas where complete examination of 100% of the required volume from one direction could not be achieved are indicated by PAR (partial) notation on the examiner's data sheet, and th.e limiting cause is noted. Code requirements will have been satisfied since 100% of the weld was examined by use of a combination of UT examin-ing directions, e
e-. 1.3 Additional non-destructive tesing required subsequent to this , revision due to modification, additions, rework, etc. shall be conducted as required. Information regarding additional examinations shall be submitted in revised issues of the pre- ' service program. If, in additional examinations, an area is found where essentially 100% of the weld cannot be examined as required by ASME Section XI, IWB-2100, relief requests
- shall be submitted which include the extent of examination performed and the primary reason a complet'e examination is impractical. Included in these relief requests will be the alternate examination method and/or supplemental examinations performed. A list of these welds will be provided following preservice inspection.
1.4 Components will be examined in accordance with ASME Section XI, Subsection IWA, IWB, IWC, and IWD.
- 1. All piping has been reviewed by SCE&G against the NRC's l Quality Groups A,B, and C which corresponds respectively I l
to ASME Section III, Class 1, 2 and 3.
- 2. All Class 1 and 2 systems and components have been review-ed by SCE&G against the respective ASME, Sectida XI, Sub-section IWB-1220 and IWC-1220 exemption criteria.
-4ll> . B-4 (Rev. 2)
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- 3. Class 3 systems and components, and exempt Class 1 and 2 components require only a visual examination during pressure testing in accordance with IWA-5000. The scoped flow drawing .
Subsection VI of this section are used during the visual examinations to aid in the location and position of any component which have reportable discrepancies during the test. 1.5 Determination of ASME Section XI, Code categories for Class 1 and' 2 components.
- 1. All Class 1 and 2 components have been categorized in accordance with ASME Section XI Table IWB-2500 and IWC-2520 respectively. These generated _. tables are included as subsection II of this section of the Preservice Plan. Also, included in this tabu- , [
lation are certain Class 2 systems or portion of Class 2 systems and component which are exempt from the examination requirements of.IWC-2520 by ' IWC-1220. Below is a summary of these exemptions as applicable to thIe'
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V.C. Summer Station: i s ra. All CVCS piping equal to or less than 4-inch nominal diameter is exempted by IWC-1220 (d). ,
- b. The boron injection system piping is equal to or less than 4-inch nominal diameter, and there-by is exempted by IWC-1220 (d). !
- c. The class 2 portion of the high head SIS piping is ,
all equal to or less than 4-inch nominal diameter and, i thereby is exempted by IWC-1220 (d),
- d. The RWST and associated piping have design gressures and temperatures less than 275 psig and 200 F and are exempt by IWC-1220 (a). ,
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- e. The containment spray system does not function ,'
during normal reactor operation and is exempted ,. by IWC-1220 (b). 1
- f. The seal water injection filter is manufactured from piping of 4-inch nominal diameter and there- J
- by, exempted by IWC-1220 (d) .
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B-5 (Rev. 2) I 1
- 2. Also, included in tabulation of Class 2 systems and components are numerous references of examination requirements that are not applicable for specific items. Following are the explanations of these exceptions:
- a. The letdown heat exchanger nozzles are 3-inch diameter and excluded by IWC-1220 (d). There are no integrally velded supports on'the Class 2 portion of the vessel and tubesheet flange bolting is 1-inch diameter and is not included in Category IWC-2520 C-D.
- b. The excess letdown heat exchanger nozzles are 2-inch diameter and thereby, exempted by IWC-1220 (d).
- c. TheregenerativeheatexchangeNnozzle are 3-inch diameter exempted by IWC-1220 (d). There are no integrally velded supports or pressure retaining ,
bolting.
- d. 1he seal water heat exchanger nozzles are 4-inch dia-meter and thereby, exempted by IWC-1220 (d). The integrally welded nozzles are on the Class 3 portf.on"" "
of the vessel and tube sheet flange bolting is 3/4 inch diameter. e' e. The steam generators do not have integrally velded supports on the secondary side.
- f. The seal wa'er t return filter and reactor coolant filter nozzles are 2-inch diameter and cover I'
bolting is 5/8 inch diameter in which case are exempted by IWC-1220 (d).
- g. The volume control tank nozzles are 4,3, and 2-inch diameter and tl .by, exempted by IWC-1220 (d).
- h. The letdown rehett heat exchanger nozzles are 4-inch diameter. There are no integrally velded supports on the Class 2 portion of the vessel and tubesheet. , 1 I
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- 1. The residual heat removal pump casings do not contain any velds, J. There are no Class 2 valves with pressure retaining welds or integrally welded supports.
~ l B- 6 (Rev. 2)
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NOTE #1: THOSE COMPONENTS NORMALLY EXEMPTED FROM EXAMINATION BY SUBSECTION IWC-1220 (c)
- HAVE BEEN INCLUDED IN THE AUGMENTED EXAMINATION PROGRAM.
NOTE #2: SOME COMPONENTS MAY BE EXEMPTED FROM PRESERVICE EXAMINATION BY UTILIZING SHOP AND FIELD EXAMINATION AND IN-STALLATION RECORD TO SATISFY PRESERVICE EXAMINATION REQUIREMENTS. THOSE EXEMP-TION WILL BE IDENTIFIED IN APPLICABLE RELIEF REQUESTS.
- 3. Circumferential butt welds in piping within'3 pipe diameters of the centerline of rigid pipe an'chors or anchors at the penetration of the primary reac-tor containment, or at rigidly anchored components >
vill be inspected per examination categories C-F and C-G of Table IWC-2520. ,
- 4. Preservf ce Inspection boundary classification are a. ,
included in Subsection VI of this section of the Preservice Inspection Plan as scoped drawings, v c .
- 5. Component Identification and Location e.1 Isometric drawings of the Class 1 and 2 systems are used as the working drawing during the inspection. These drawings are included in Subsection 7 of this section of the Preservice Plan. The drawings contain the following in-formation.
- a. Piping line number
- b. Location and identification of all circumferential and longitudinal welds,
- c. Location and identification of full penetration welds to the pressure-retaining boundary.
- d. Location and identification of flange connections.
il e. All identification numbers which are specific to each examined components. . B.7 (Rev. 2) 1
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k , t b [\ ' i Q;I h 1.6 Preservice Component Inspection
.1. The Preservice Inspecti.on serves as a baseline for- [
- futura. inservice inspections. ;
i When examination requirements of an ASME Code Class 2. 1, 2,'or 3 component is impr'actical to accomplish l in accordance with respective ASME Section XI, !
-IWA-2000, IWB-2000, IWC-2000 or IWD-2000; a specific i written relief request from the ASME Code shall be submitted to the NRC (in accordance with A above).
- i Each written relief request will contain, as a l minimum, the following information
- a. Identification of component (s) for which
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relief is requested. *
- b. ASME Code Class i
- c. The specific AMSE Code requirements that ,
cannot be accomplished. l d. i Justification (s) for relief request. i
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- e. Alternate examination to be performed in lieu of ASME Code requirement (s). ?
, ec
- 1.7 All records and reports are prepared in accordance with ASME, ;
Section X1 IWA-6000, except those items being identified in ; the relief request in which case a modified report is prepared. l s i 1.8 Augmented Examination Program j NOTE: THE AUGMENTED INSERVICE INSPECTION TO ENSURE THAT : THE REACTOR VESSEL AND ESSENTIAL EQUIPMENT WITHIN ! OR OUTSIDE OF THE CONTAINMENT, INCLUDING COMPONENTS OF THE REACTOR COOLANT PRESSURE BOUNDARY, AND OTHER l
,i SAFETY-RELATED COMPONENTS HAVE BEEN ADEQUATELY PRO- {j TECTED AGAINST POSTULATED PIPING FAILURES HAS BEEN *i INCLUDED IN THE PRESERVICE INSPECTION PROGRAM AND l THEREFORE WILL NOT BE DISCUSSED HERE. lj k
t'
- 1. Components normally exempted from examination by Sub- li r' ' section IWC-1220 (c) have been included in this Augmented i
- Examination Program. Isometric drawings have been in- !
eluded and identified ar I.srt of the Augmented Exam,ination ! Program. L r! h 4 ^. B-7A (Rev. 2) I , ( .... _ _ , . ....._. . _ . . . . . . . . . . - - .
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- 2. Steam Generator Tube Examinations
- a. Preservice Inspection of steam generator tubes will be performed in accordance with ASME Code Section XI 1977 Edition through 1978 addenda in order to comply with NRC Regulatory Guide 1.83, Revised 1, July 1975.
- b. Preservice Inspection involves an axsmination of the full length of each tube in ca h Steam Generator by Eddy Current techniques prior to' service to establish a baseline condition of the tubing and verification by the ANII,that all requirements have been met.
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- c. The examination will be performed af terthe field hydrostatic test and prior to intial power operation using the equipment, and techniques expected to be used during sub-sequent inservice inspections. ,
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. IWB-2600 .IWB-2500 WELD NAME N UMB Ell EXAMINATION REFERENCE REMARKS $"*-l I ITEM OF ITEMS METHOD DRAVING .
} NUMBER CATEGORT (DESCRIPTION) (ISOMETRIC) 24.5 B-J CIRCUMFERENTIAL AND 1001 'UT(1001 Volume) CCE-1-4100 LONCITUDINAL PIPE WELDS thru CCE-1-4506-l .
B4.6 B-J BRANCH PIPE CONNECTING 6 (1001) UT(1002 Volume) CCE-t-4101
~
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> 6"
- 8 CCE-1-4102, l
CCE-1-4500, CCE-1-4201, to CCE-1-4301 & l8 s" CCE-1-4302 , \ t-84.7 B-J BRANCH PIPE CONNECTING !? (1301) PT(1001 Surface) CCE-1-4103
^ 6" DIAMETER AND SMALLER thru gh ,
CGE-1-4107, g <: CC F.p l- 410 9, CC 1-4504,
,u ,
CC 1-4202 ,
*V thru ,
CCE-1-4205,
- i CCE-t-4207,
- CCE-t-4208, CCE-t-4303
. thru i
? CCE-1-4305,-
CCE-1-4307 CCE-1-4308, i *
, CCE-1-4508 8 B4.8 B-J SOCKET VELDS 1002 PT(1001 surface) CCE-1-6100 ~
I thru - CCE-1-4506
+ b s #
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l ' V. C. SUMMER PRESERVICE INSPECTION PROGRAM - CLASS 2 COMPONENT .j ' IWC-2600 IWC-2520 WELD NAME NUMBER EIAMINATION REFERENCE. ITEM REMARKS - OF ITEMS ,f NUMBER CATECORT (DESCRIPTION) METNOD DRAWING (ISOMETRIC)
,I C3.2 C-D PRESSURE RETAINING BOLTING UT(1002 Volume)
VT(1002) C3.3 C-E-i ' INTEGRALLY WELDED SUPPORTS ' iI PT(1003 Surface)
- a C3.4 C-E-2 SUPPORT COMPONENT VT(1001)
I I ( PIPING I C2.1 C-P CIRCUMFERENTIAL BUTT WELDS C-C
- UT(1001 Volume) CCE-2-2100
-l CCE-2-2803 'tl ts C2.2 C-F LONCITUDINAL WELDS IN 8
- C-C PITTINGS UT(1001 Volume) CCE-2-2100 ___
, 12 CCE-2-2803
~
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- I .1.n C2.3 C-P t lj n RRANCE PIPE TO PIPE WELD UT(100I Volume) CCE-2-2101 C-C JQINTS '
~ ~ ~ ~~ -
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[l-@ C2.4 C-D PRESSURE RETAININC BOLTING *
'f- EXCEEDINC>l" DIAMETER .
UT(1002 Volume) VT(1003) CCE-2-2101
- l k k U' C2.5 C-E-1 INTECRALLY WELDED SUPPORTS PT(1003 Surface) ' -
C2.6 C-E-2 Q ' i, SUPPORT COMPONENTS VT(1001)' o r VALVES
. C4.1 C-P. VALVE BODT WELDS N/A I! -
C-C THERE ARE NO ITEMS IN TNIS CATECORY 8
._-...___...-.~-......,.__...,__.s-. _ . .. . _ . . . . . . . , . _ , . . _ . -.m._.-.--. . _ . . ~ . . . . . . , . . . . . _ . . _ . - , . _ . . . . . - . , . _ . - . . . . . . . . . . . . _ _. .
4 r3 V e -. (THIS PAGE HAS BEEN DELETED) (S.
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l 'j 4 2 l l i B-32 (Rev. 2) > p y .,y---,- -,
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W" f I i t 1 i t ene l (THIS PAGE HAS BEEN DELETED) 1 I Cia - j uc . 1 4 ll l 1 e i 2
.I 1
l B-41 ( REV. 2) ?. d
. . . . . . . . . . . . . ~ . . .... . . - .. - - - - - . . . . . . .. .. ... .. .. .. .
. . . ~ -. - . . . - -_ . .~. -- . . . , - . . . - . .~ - .
7 r t PSI WELD REFERENCE INDEX +
-i i
t PSI FILE NO. CODE CLASS SYSTEM DESCRIPTION FLOW DWG NO. CGE-1-11100 .' 1- RC Reactor Vessel N/A i i CGE-1-1110 1 RC . Reactor Vessel Clad N/A j i
.CGE-1-1120 1 RC Reactor Vessel Head N/A !
CGE-1-1200 1 RC Reactor Internals N/A j CGE-1-1310 -1 RC CRDM Housing . N/A j i CGE-1-1400 1 RC - Reactor Vessel Studs N/A CGE-1-2100 1 RC Pressurizer N/A CGE-1-3100- 1 RC Reactor Coolant Pump N/A : CGE-1-4100 1 RC Reactor Coolant 114E072 Loop 1- !
.}
~ CGE-1-4101 ' 1. RC Acc. Disch to RC Loop 1 114E072 ,!
N# "' " CGE-1-4102 1 RC RHR Takeoff AC Loop 1 114E072 i CGE-1-4101 i RC Acc. Disch to RC Loop 1 114E072 e i
.we i:
ij CGE-l-4102 1 RC RHR Takeoff RC Loop l' 114E072 t CGE-1-4103 SI C.L. To RC Loop 1 114E072
^
1 RC li CGE-1-4104 1 RC SI H1/Lo HD to RC 114E072 - ~ Loop' 1 { CGE-1-4105 1 RC RTD Mainfold to RC Loop 1 114E072 CGE-1-4106 1 RC ALT Charging to RC. Loop 1 114E072 , CCE-1-4107 1 RC Letdown RC Loop 1 114E072 , CGE-1-4108 1 RC RC Loop 2 RTD Takeoff 114E072 It CGE-1-4109 1 RC RC Loop 2 RTD C.L. 114E072 ) CGE-1-4110 1 RC RC Loop 1 Drain Line 114E072 CCE-1-4111' 1 SI SI High HD to RC Loop 1 114E075 ;,
) -
t, ;,
. B-43 (Rev. 2) ]
1
~ , . , ,......,=-,..% . # . .
- 7. .y . .. . . . , _ , ., , , , . , ,
I i l PSI FILE NO. -CODE CLASS' SYSTEM DESCRIPTION FLOW DWG NO. ] CGE-1-4112 .- l' SI High Head CL to RC 114E075 Loop 1 1 CGE-1-4113' l' SI High Head to RC Loop'1 114E075 l
'CGE-1-4114 1 RC RC Loop 1 Seal Inject 114E07
]
l CCE-1-4200 1- RC Reactor Coolant Loop 2 114E072 l l CGE-1-4201 1 RC Acc. Disch to RC L'oop 2 114E072 1
-)
CGE-1-4202 1 RC SI Hi/Lo HD C.L. to RC 114E072 i Loop 2 CGE-1-4203 1. RC SIHi/LotoRCYoop2 114E072. l CGE-1-4204 1 , RC. RTD Return to RC Loop 2 114E072 l l CGE-1-4205 1 RC Normal Changing to RC 114E072 Loop 2 ~. CGE-1-4206 1 RC RTD Takeoff RC Loop 2
- 114E072
'CGE-1-4207 1 RC RTD C.L. RC Loop 2 114E072 CGE-1-4208 1 RC RC Loop Drain Line 114E072 CCE-1-4209 1 SI High Head to CL for RC 114E075 Loop 2 l CGE-1-4210 1 SI High Head to CL for RC 114E075 Loop 2 ,
CGE-1-4211 1 SI High Head to CL for RC 114E075 Loop 2 CGE-1-4212 1 RC Loop 2 Seal Injection 114E075 CGE-1-4300 1 1 RC RC Loop 3 114E072 CGE-1-4301 1 RC Acc. Disch to RC Loop 3 114E072 CGE-1-4302 1 RC RHR Takeoff 114E072 CGE-1-4303 1 RC SI High Head C.L. to RC 114E072 Loop 3 CGE-1-4304 1 RC SI Hi/Lo HD to RC Loop 3 114E072 - CGE-1-4305 1 RC RTD Return to RC Loop 3 114E072 E-44 (Rev. 2)
PSI FILE NO. CODE CLASS SYSTEM DESCRIPTION FLOW DWG.NO. CGE-1-4306 . 1 RC RTD Takeoff RC 114E072 Loop 3 CGE-1-4307 1 RC RTD C.L. fo RC Loop 3 114E072 CCE-1-4308 1 RC RC Loop 3 Drain Line 114E072 CGE-1-4309 1 SI SI High HD to RC Loop 3 114E075 CGE-1-4310 1 SI High Head to RC Loop 3 114E075 CGE-1-4311 1 SI SI Hi/Lo to RC Loop 3 114E075 CGE-1-4312 1 RC L'oop 3 Seal Injection 114E075 CGE-1-4500 1 RC Pressurizer Surge Line 114E072 CGE-1-4501 1 RC Pressurizer Relief Line 114E072 CGE-1-4502 1 RC Pressurizer Safety 114E072 Relief Line L -, CCE-1-4503 1 RC Pressurizer Spray Line 114E072 CCE ,1-4504 e c 1 RC Pressurizer CL Spray, 114E072 CGE-1-4505 1 RC Pressurizer Relief Line 114E072 CGE-1-4506 1 RC Aux. Spray Line 114E072 CGE-1-5100 1 RC RCP Flywheel N/A l CGE-1-5110 1 RC RCP Flywheel N/A -l l CGE-1-5120 1 RC RCP Bolting N/A CGE-2-1100 2 MS Steam Generator N/A CCE-2-1200 2 CS Volume Control Tank 114E073 CGE-2-1300 2 CS Seal Water Injection 114E073 Filter CG E 1310 2 CS RC Filter 114E073 CGE-2-1320 2 CS Seal Water Return 114E073 Filter B-45 (Rev. 2)
~
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. l l
i
.[ PSI' FILE NO. CODE CL'US SYSTEM DESCRIPTION FLOW DWG NO.
CGE-2-1330 .2 CS Letdown Heat 114E073 Exchanger CGE-2-1340 2 CS Seal Water Heat 114E073 Exchanger i CGE-2-1350 2 CS Letdown Reheat 114E073
. Exchanger .
I CGE-2-1360 2 CS Regenative Heat 114E073 Exchanger - CGE-2-1370 2 CS Excess Letdovn. Heat 114E073 Exchanger .; CGE-2-1380 2 RH RHR Heat Exchanger 1145074 CGE-2-2100 2 MS Loop A to Penetration D-302-D11 428 .
~
CGE-2-2001 2 MS Loop A From Penetration D-302-D11 428 CGE-2-2102 e c . 2 - FW Loop A from Penetration D-302-083 306 to SG "A" CdE-2-2103 2 FW Loop A from Flow Nozzel D-302-083 to Pen 306 -j CGE-2-2104 2 FW Loop A 18" Piping D-203-083 CGE-2-2105 2 MS Loop A Relief Line D-302-011 CGE-2-2106 2 MS Loop A Steam Dump D-302-031 CGE-2-2107 2 FW Loop A 6" Aux Feed D-302-085 CGE-2-2200 2 MS Loop B to Penn 207 D-302-011 CGE-2-2201 2 MS Loop B from Pen 207 to D-302-011 XVT-2801B j CGE-2-2202 2 FW FD Water Loop B D-302-083 l
.CCE-2-2203 2, FW Loop B 18" Pipe D-302-083 I C) .
r l B-46 (Rev. 2) ;
PSI FILE NO. CODE CLASS SYSTEM DESCRIPTION FLOW DWG NO. CGE-2-2204 2 FW Loop B 6" Aux Feed D-302-083 CGE-2-2300 2 MS Loop C to Penn 202 D-302-011 CGE-2-2301 2 MS Loop C from Penn 202 D-302-011 CGE-2-2302 2 MS Loop C 24" Line to D-302-011 XVT-2801 C CGE-2-2303 2 FW Loop C from Penn 203 D-302-083 to SG "C" CGE-2-2304 2 FW Loop C from Flow Nozzel D-302-083 to Penn 203 s CGE-2-2305 2 FW Loop C from IFV-3341 to D-302-083 Flow Nozzel J CGE-2-2306 2 MS Loop C Relief Line D-302-011 CGE-2-2350 2 MS Loop C 30" Line D-302-011 ( CCE-2-2351 2 FW CL Header from Feed cu D-302-082 . Heaters CGE-2-2352 , < 2 FW 6" Aux Feed Loop C D-302-083
. I CGE-2-2500 2 RH Loop A Pump Suction 114E074 ,
I CGE-2-2501 2 RH Loop B Pump Suction 114E074 j' CGE-2-2700 2 RH Loop A Pump Disch 114E074 , CGE-2-2701 2 RH Loop B Pump Disch 114E074 - CGE-2-2702 2 RH RER to RHR Heat Ex. A 114E074 CGE-2-2703 2 RH Heat Exhanger A to Penn
~
322 CGE-2-2704 2 RH Heat Exhanger B Outlet 114E074 to Penn 325 CGE-2-2705 2 SI RHR Heat Ex. "B" Out to 114E075 Penn 227 CGE-2-2 706 2 SI RHR C.L. Return Hi/Lo 114E075 Recirc from Penn 322 to l' (E(')
-# RC Loop A - !'
B-47 (Rev. 2) l'
i
. I 1
~
[ PSI F'ILE NO. _C0DE CLASS SYSTEM- DESCRIPTION FLOW DWG NO. ') j CGE-2-2707 2 SI SI to RC Loop B 114E075
- j
- CGE-2-2708 2 'SI SI from Pen 227 to 114E075 RC Loop C .
CCE-2-2800 2 CS Chg. Pump A B & C 114E073 ] Suction Line 1 l CGE-2-2801 2 CS . Chg. Pump A B & C 114E073
-' Suction Line from
, VCT ]
i . CGE-2-2802 2 RH , Heat Exchanger A 114E074 l to CVCS e .- CGE-2-2803 2 RH Heat Exchanger B to -114E074
~
CVCS t
'CGE-2-3100 2 RH . RHR Pucps A&B 114E074 Cent Charge Pumps
[ CGE-2-3110 2' CS 114E073
,, c (AUGMENTED PROGRAM)
CGE-2-0001 2 , SP RB Spray System D-302-661' CGE-2-0002 2 SP RB Spray System D-302-661 CGE-2-0003 2 SP RB Spray System D-302-661 ;I I I CGE-2-0004 2 SI Safety Injection 114E075 ., Ii CGE-2-0004 2 SI SI Accumulator Disch 114E075 CGE-2-0006 2 SI Boron Injection System 114E073 i iJ CGE-2-0007 2 SI SI Accumulators 114E075 CGE-2-0008 2 SI Boron Injection Tank 114E073 B-48 (Rev. 2) _ _ . _ - re-w e W ,.6- ,+-
4 e O
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. I i
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lI B-49 (Reve 2) i
)1 i i
- 6- e ee eee o+ p6- 6 de**ume we m gene e *
- M eme 6 4 =d, . g . ,4 e og . , ,. g. ) ,,,p, g , g , , , , ,
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l c i i I
"' l PSI FILE NO.TO VELD NO.INDEX -
i
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QQ PSI FILE NO. WELD NO. DESCRIPTION SYSTEM CGE-1-1100 1 through 11 Reactor Vessel RC CGE-1-1110 . CP-1.through CP-8 Reactor Vessel Clad RC CGE-1-1120 CP-1 through CP-6 Reactor Vessel Head RC CGE-1-1310- Housing Welds (24) .CRDM Housing Welds RC CCE-1-1400 R.V. Studs, Nuts & Reactor Vessel Studs RC Washers (58) CGE-1-2100 #1 through # 14 Pressurizer RC CGE-1-3100 CP-1 through CP-3 Reactor Coolant' Pump RC and Bolts 1 through - 32 e -. CGE-1-4100 3,4,5DM, 6DM, 7 RC Loop 1 RC, through 13, 18BC, 25BC, 26BC CGE-1 4101 1 through 21 Acc Disch to RC Loop 1 RC . C-), . CGE-4102 1 through 23 RHk Takeoff Loop 1 RH CGE-1-4103 1 through 16 -SI C.L. to Loop 1 SI y C
- CGE-1-4104 1 through 21 SI HI/LO HL to Loop 1 SI CGE-1-4105 1 through '28 RTD Manifold to Loop 1 RC CGE-1-4106 1 through 10 ALT. Charging to Loop 1 CS ;.
i' CGE-1-4107 1 through 15 Letdown Loop 1 CS CGE-1-4108 1 through 18 Loop 2 RTD Takeoff RC l 1 CGE-1-4109 1 through 24 Loop 2 RTD C.L. RC I CGE-1-4110 1 through 6 Loop 1 Dra1n Line RC. CGE-1-4111 1 through 40 SI High HD to Loop 1 SI CCE-1-4112 1 through 12 HI HD C.L. to Loop 1 SI 6
.k i iI l
B-51 (Rev. 2)
......w,.-........ . . . . . . . . _ . . . ,_. . . . . . . . .
l j I IO' iL- - PSI FILE NO.~ WELD NO. DESCRIPTION SYSTEM t
~
,, CGE-1-4113 :1:through.1:2 HI HD to Loop l' SI !
CGE-1-4114 - 1.through 12 SealInjection to RCP 1- CS , CGE-1-4200' I through 23 RC Loop 2 RC. f CGE-1-4201 WS-1, WS-2, Loop 2 Ace Discharge SI 1 through 13 .. CGE-1-4202 1 through 20 SI HI/LO HD C.L. to Loop 2: SI ! CGE-1-4203 1 through 20' SI HI/LO to Loop 2 SI ! CGE-1-4204 1 through 24 RTD Return to Ldop 2 RC CGE-1-4205 I through 12 Normal Charging to Loop 2 CS l CGE-1-4206- 1 through 17 RID Take'Off Loop 2 RC, l t CGE-1-4207 1 through 24 RTD C.L Loop 2 RC CGE-1-4208 1 through 9 Loop 2 Drain Line RC .t CGE-1-4209 1 through 24 HI HD to C.L. for Loop 2 SI j
.CGE-1-4210 1 through 9 & 10 HI HD 'to C.L. for Loop 2 SI :
v# BC . j
~
CGE-1-4211 1 through.15 & 16 HI HD to Loop 1 SI i BC ! i,
.CGE-1-4212 1 through 10 Seal Injection RCP 2 CS' jf CGE-1-4300 1 through 24 RC Loop 3 RC .
i CGE-1-4301 1 through 13 Acc. Disch to RC Loop 3 RC s! CGE-1-4302 1 through 24 RHR Takeoff RH l t CGE-1-4303 1 through 18, SI HI HD C.L. to Loop 3 SI, l WE-1, WS-2 j CGE-1-4304 1 through 8 SI HI/LO HD to Loop 3 SI 'l !
'CGE-1-4305- I through 26 RTD Return to Loop 3 RC i
'l
- j
>~4
;J e
1 i i
. B-52 (Rev. 2) !
l a f
.b # PSI FILE NO. WELD NO. DESCRIPTION SYSTEM CGE-1-4306 1 through 18 RTD Takeoff Loop 3 RC ,
CGE-1-4307 . I through 28 RTD C.L. Loop 3 RC CGE-1-4308 1 through 11 Drain Line Loop 3 RC CGE-1-4309 1 through 26 HI HD to Loop 3 SI t CGE-1-4310 1 through 8 HI HD to Loop 3 SI CGE-1-4311 .1 through 53 SI HI/LO to Loop 3 - SI
'CGE-1-4312 1 through 10 Seal Injection RCP 3 CS CGE-1-4500 1 through 13 PZR Surge Line RC ,
CGE-1-4501 1 through 33 PZR Relief Lir.a RC I
~
CGE-1-4502 1 through 21 PZR Safety Relief Line RC CGE-1-4503 1 through 43 PZR Spray Line RC
,e s
() CGE-1-4504 1 through 30 PZR C.L. Spray Line ,_ RC . OGE-1-4505 1 through 8 PZR Relief Line RC CGE-1-4306 '. 1 through 18 Aux. Spray Line , CS ? CCE-1-5100 N/A
- RCP Flywheel RC I CGE-1-5110 N/A RCP Flywheel RC -
CGE 1100 1 through 11 SG "A" "B" & "C" MS CGE-2-1200 1,2, WS-1, WS-4 VCT CS CGE-2-1300 'N/A Seal Water Injection Filter RC ' CCE-2-1310 1,2, WS- 1, WS-2, - Reactor Coolant Filter RC WS-3 & WS-4 CGE 1320 1,2, WS-1, WS-2, Seal Water Return Filter .CS ll WS-3 & WS-4 CCE-2-1330 1&2 Letdown Heat Exchanger CS CGE-2-1340 1&2 Seal Water Heat Exchanger CS 1 B-53 (Rev. 2)
i yy (_.) PSI FILE NO. WELD NO. DESCRIPTION SYSTEM
. CGE-2-1350 1&2 Letdown Reheat Exchanger CS CGE-2-1360
- 1,through .10 Regenative Heat Exchanger' CS CGE-2-1370 1, WS-1 & WS-2 Excess Letdwon Heat CS Exchanger CGE-2-1380 1 through 4 RHR Heat Exchange A & B RH CGE-2-2100 1-1, 1-2, 1- 2A, 1-7 Loop A to Penn. 428 MS CGE-2-2101- 1-56, 1-11, 1-25, Loop A to XVT-2801A MS 4-1, 4-1A, 4-2, 4-2A 4-3, 5-1, 1-51, 1-26 CGE-2102 1-1 to 1-18, WS-1, Loop A from Penn. 306 to. FW WS-2 SG "A" CGE-2-2103 121, 123 Loop A from Flow Nozzel FW to Penn 306 f"~g CCE-2-2104 1-29, 1-30, 1-43, Loop A 18" Piping FW .
( ,) - 1-52, 1-64, 1-67 cu ,, CGE-2-2105 1-39 Loop A Relief Line MS < l
,CCE-2-2106 1-52 Loop A Steam Dump MS CCE-2-2107' 1 Loop A 6" Aux. Feed FW
')
CGE-2-2200 2-8 Loop B to Penn 207 MS CGE-2-2201 2-15, 2-17, 2-22, Loop B from Penn 207 MS 2-22A 2-28, 2-32, to XVT-2801B 2-40, 2-45 CGE-2-2202 2-1 through 2-14, Loop B from Penn 206 FW l WS-1, WS-2 to SG "B" CCE-2-2203 2-18,2-19,2-20 Loop B 18" Pipe FW 2-40, 2-44, 2-60, . 2-61 CGE-2-2204 2-34 Loop B Relief Line MS CGE-2-2205 3 Loop B 6" Aux Feed FW (S, . .
\~) -
B-54 (Rev. 2)
. . _ . . _ . - . . , . .. .. 1
6: , . I b l(^$ b
."\~) ,
PSI FILE NO.
~ 'A-WELD NO. DESCRIPTION SYSTEM 3 i
CGE-2-2300 3-10 Loop C to Penn 202 MS CGE-2-2301 . 3-13, 3-19A, 3-20, Loop C from Penn 202 MS
. 3-21, 3-23, 3-29, ;
3-30, 3-31, 3-37, , 3-40, 3-46, 4-3 } through 4-11_ . CGE-2-2302 9-1 through 9-6 Loop C 24" Line to MS : XVT-2801C , j CGE-2-2303. 3-1 through 3-26 Loop C from Penn 203 . FW-. J to SC "C" i
. 6
~CGE-2-2304- FW-1, FW-3 Loop C from Flow Nozzel FW f ws.1,ihFW-7 throu - to Penn. 203 }
CGE-2-2305 3-39, 3-41, 3-43, Loop C from IFV-3341 to FW } 3-44, 3-7, 3-51, Flow Nozzel ; 3-55, 3-57 : CGE-2-2306 3-40 Loop C Relief Line MS . CE-2-2350 . ' 5-1, 5-2A,6-2,7-3A, Loop C 30" Line MS f 7-4, 8-5 ;
, I CGE-2-235L c .
4-1 through 4-14 C.L. Header from Feed FW j Heaters ,j CGE-2-2352 4 6" Aux. Feed Loop C FW CGE-2-2500 3,4,6,6A,7,8A,9, Loop A Pump Suction RH' i 15,16,18 through 25, 28, 29, 31 . through 35, 42, 155 through 158 i CGE-2-2501 166 through 171 Loop B Pump Suction RH I 177 through 180 183 through 195 j 201A, 307 1 CGE-2-2700 50,52 through Loop A Pump Discharge 'IGI 55,-57, 58, 58A, 61 through 70, 73, 76, 76A, 77 o -
- 1 B-55 (Rev. 2)
, , y
- v. .
I j ; PSI FILE N'O. . k' ELD NO. DESCRIPTION SYSTEM
, -i CGE-2-2701 204,.209, 211 Loop B Pump Discharge RH -[
through'214, 216 ;
- through 220, 227 ~
through 230, 233A i through 236, 238 i r
,CGE-2-2702 83 through 86, 88, RHR to RHR HT Ex. "A" RH l 91,.92, 92A, 95, 96, -!
99, 148 through 150- l
,CGE-2-2703; 92,92A,95,96,99 Heat Exchange "B" to . SI through 104, 110 Penn 325 through 117,.123 ,
thr.ough 125, 128 *
.l through 130, 133 j 134, 141,.141A, 149 '
- 150, 364 through 366 376, 377 ;
CGE-2-2704 245A through 249A Heat Exchange "B" to SI 252, 255, 258, 259, Penn 325- - : 259A, 263 through ! 268, 273, 273A, 296 . ,
% through 301, 364 through 379 t
CGE-2-2705 # 273 through 280 RHR HT. EX "B" to Penn SI ! 283 through 288 227 i 296 through 298 -! l CGE-2-2706
^
312 through 315 RHR C.L. Return HI/LO SI ! Recire from Penn 322 { to RC Loop A i CGE-2-2707 321, 322, 329 SI to RC Loop B SI I through 331, 339 ! through 341, 347, , 350 , CGE-2-2708 353, 355, 356, 359,. SI from Penn 227 to RC SI I 360 Loop C ,] CGE-2-2800 280, 381, 318A, 385 Chg. Pump A,B&C Suction 'CS 394,395,395A,417 - , 418,420,421,423, 424, 446, 447,451A 452, 454, 461S
.through 463 B-55A (Rev. 2)
?. -:r . . . 7 4
. ( )' '
PSI FILE NO. ~ WELD'NO. DESCRIPTION SYSTEM (- . CGE-2-2801: 399A,400,406 Chg. Pump A,B&C CS through 411~, 433 Suction from VCT
. through1435, 438, 439, 442, 443,, * ~ ~
445, 445A, 467, 467A, 469
- CGE-2-2802 '145, 420 through Heat Ex. "A" to CVCS RH
? 474, 479 through. , 481 CGE-2-2803- '306,486,489, 489A ' Heat-Ex. "B" to CVC5 RH 490, 491, 491A, 496, through 505 -
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'i C. HYDROSTATIC TESTING 7 The Planned Preservice (Baseline Data). Inspections i
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Preservice (Baseline Data) Hydrostatic Testing will be - conducted during the construction and start-up (Phase I Testing) of V.C. Summer Station Utilizing"the Phase'I test ; procedures. [ r f; NOTE: The PSI File Numbers in the following section are g , , also the Phase I Hydrostatic Test Procedure number. i: L. - p? The following section identifies those hydros whose l scheduled test and inspection boundaries contitutes code , hydros. This list is subject to revisions periodically due to changes caused through the start up phase. A final ! i list fo preservice code hydros will be generated and sub- I
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. .i!-1 PSI IlYDRO REFERENCE INDEX *j CODE .
CLASS SYSTEM' DESCRIPTION FL0tJ DWG > PSI . FILE { AH-02-H1 2 AH~ RB Purge Supply Pneumatic Test D-912-103 l
'AH-03-H1- 2 AH RB Purge Exhaust Pneumatic Test D-912-103
-i CC-01-H1 3' CC Component Cool Low Pressure Hydro D-302-611 s CC-02-H1 3 CC Component Cool Surge Tnk Hydro D-302-611 CC-04-H1 2/3 CC Component' Cool to Thermal Barr D-302-612 ;
CC-04-H2 2/3 CC CC Boost Pmp Inlet to Bar Efdro D-302-612 l
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*I Hydro Q.W .
CS-02-H3 3 CS Makeup Piping Hydro 114E073 CS-03-H1.< 2 CS Charging Pump Discharge Pipe 114E073 Hydro CS-04-H1 2 . CS - Charging Header Hydro 114E073 CS-05-H1 2 CS Seal Injection Piping Hydro 114E073 , CS-07-H1 2 CS RC Pump Seal Return Lines Valve 114E073 CS-07-H2 2 CS RC Pump Seal Return Lines Valve 114E073 CS-07-H3 2 CS RC Pump Seal Return Valve S100 114E073 CS-09-H1 1 CS ~ Excess Letdown Hydro 114E073 CS-09-H1 1 CS High Pressure Letdown Hydro 114E073 i CS-11-H1 2 CS Lordown Line IP Hydro 114E073 CS-12-Ill 2/3 CS Letdown LP Demin Hydro 114E073 h CS-13-H1 2 CS BCMS Hydro 114E073 ! j CS-17-H1 3 CS Eoric Acid Transfer Pumn Suction 114E073 l' 4 C-5 (Rev. 2) l 3
, P,51 HYDRO REFERENCE INDEX i CODE j
PSI FILE # CLASS SYSTEM DESCRIPTION FL,0W DMG CS-17-H2 3 CS Boric Acid Transfer Pump 114E073 Discharge CS-17-H3 - 2 CS Boric Acid Stroe' Tanks Hydro 114E073 CS-20-H1 3 BR BRTS Demineralizer Hydro 114E076 CS-21-H1 3 BR Holdup Tank Header Hydro 114E076 CS-22-H1 3 BR Holdup Tank Eductor' Hydro 114E076 CS-23-H1 3 BR Recycle Evap Feed Demin Hvdro 114E076 CS-24-H1 3 BR Recycle Evap Hydro 114E076 CS-26-H1 3 BR CVCS Holdup Tanks Hydro 114E076
~
CS-26-H2 3 BR CVCS Holdup Tank 114E076 CS-26-H3 3 BR CVCS Holdup Tank 114E076 CS-27-H1 3 BR CVCS Safety Valve Discharge 114E076 Header h DG-02-H1 3 DG D/G Fuel Oil Storage Tnk A Pipe D-302-351 Hydro DG-03-H1 ' 3 DG ,D/G Fuel Oil Storage Tnk B Pipe D-302-351 Hydro DG-04-H1 3 DG D/G "B" Day Tnk & Pipe Hydro D-302-351 DG-05-H1 3 DG D/G "A' Day Tnk & Pipe Hydrolve D-302-351 DC-08-H1 3 DC D/G "A" Starting Air D-302-353 DG-09-H1 3 DG Diesel Gen "B" Starting Air D-302-353 DG-10-H1 3 DG Diesel Gen "A" Crankcase Vac Lk D-302 353 DG-11-H1 3 DG Diesel Gen 'B" Crankcase Vac Lk D-302-353 DG-12-H1 3 DG Diesel Gen "A" Jacket Cool Water D-302-353 , DC-13-H1 3 DC Diesel Gen "B" Jacket Cool Water D-302-353 DN-03-H2 2 DN Demin Water RB Penetration #231 D-302-715 (. , - !l '
. \
%,) 1 I C-6 (Rev. 2)
~ . ._ 4 . . _ . ..~
~
b.
~
' PSI HYDRO REFERENCE INDEX lII- CODE-PSI FILE # CLASS SYSTEM DESCRIPTION - FLOW DWG-t EF-01-H1 ,
- 3. EF Emer FW Pumps & Suction Headers D-302-085 ;
' EF-02-H1, 3- EF Emer FW Pumps Discharge Header D-302-085 !
FH-02-H3 '2 FH Spent Fuel Trans. Tube Lkdet D-302-421 { Pneum i FS-01-H1- '2 FS ' Fire Protection Sys EUB Pen #404 D-302-231-FS-19-H2 2 FS Fire P,rotection Sys RB Pen #427 D-302-231 i
'FW-01-H1 2 FW Hydrotest'of FW Nuclear Lines 'D 302 083 l
GH-02-H1 .3 WG Wastegas Comp Suct Hd & Recire ' 114E077 ;
}
GH-03-H1 3 WG Wastegas Delay Tank & Pipe Leak . ll4E077 I i GH-04-H1 T3 WG Wastegas Shutdown Tanks Leak II4EQ77 1 HR-02-H1 2 HR Postaccident Hydrogen Vent' Hydro D-302-861 ! HR-03-H1 2/3' HR Postaccident Gas Sampling Hydro D-302-861 HR-03-H2 2/3 HR P'sto Acc H2 Gas Sample System D-302-273 ; _i IA-08-H2 ' 2 'IA Hydrotest RB Penetration #319 D-302'273 f IA-11-H2 2 . IA Hydrotest Rebu Instr Air Pen-311 D-302-273 : I
- LR-01,02,03 2 LR Leak Rate Test Sys Pneumatic Test D-302-273 l 04-H1 !
MP-01-H1 1 MP Pent. Seal Ring Test D-302-241 ,
. KP-01-H2 2 MP Mechanical Pentration Pneumatic D-302-241 Test ,
t MS-01-H1 2/3 MS Main Stm & Stm Generator Hydro D-302-011 ., I! MU-02-H1 2 MU Reactor Mkup F/Degassifier Hydro Dl302-791 ;' i I MU-03-H1 2 MU Reactor Mkup Water Stor Tank D-302-791 'i j Hydro l 1 MU-04-H1 2 MU Reactor Mkup Water Distcode Pipe D-302,791 j 1 MU-04-H2 2 MU' Reactor Mkup Water Supply to WD D-302-791 I Hydro , I i C-7 (Rev. 2)
***W W '4" N "O Y *%-- M vg s e, yg
4 . J i. PSI HYDRO REFERENCE INDEX C
,j
'V' CODE PSI FILE # CLASS SYSTEM DESCRIPTION F_ LOW DWG,
, ND-35-H1 -2 ND Incore Instr Sump & Piping D-302-821 Hydro NG-01-H2 2 NG Hydro Test Nitro Blanket Pen D-302-311.>
#313 RC-01-H1 1 RC Reactor Coolant System Cold Hydro .
114E072 RC-01-H2 2 RC Reactor. Vessel Leakoff Hydro 114E072 RC-02-H1 2 RC Pressurizer Dead Weight Tester 114E072 Hydro , RC-03-H1 1 RC RTD Bypass l' oops Hydr 114E072 e.- RC-05-H1 2 RC RC Pump Stand Pipe Makeup Hydro 114E072 RC-08-H1 f RC Reactor Vessel Head Vent Hydro 114E072 RC-06-H3 3 RC Pressure Relief Tan'k Hydro 114E072 p, RH-01-H1 2' RH Res He Removal Suction Piping m 114E074 (v) ,.
' SA-03-H2 2 SA Hydrotest RB Penetration #310 D-302- 241 SA-08-H2 2 'SA Inner Door Seal Pneumatic Test D-302 242 SA-09-H2 2 SA Emergency Personnel Hatch Inner D-302-242 SA-08-H3 2 SA Personnel Hatch Air Conn. Pneum D-302 242 SA-07-H2 2 SA Service Air to Equipment Hatch. D-302-242 SA-09-H3 2 SA Emergency Personnel Eatch D-302-242 Pneumatic SF-01-H1 2 SF RWST Hydro Test 'D-302-651 SF-01-H1 2 SF SF Cool Hydro Test D-302-651 SF-04-H1 2 SF Refueling Cavity Hydro' Test D-302-651 ,;
1 SI-01-H1 1 SI Safety Inject Highhead Piping 114E075 l l
.f s C-8 (Rev. 2)
4 di PSI HYDRO REFERENCE INDEX 3
'l
. CODE ,
PSI FILE # CLASS SYSTEM DESCRIPTION FLOW DWG. SI-02-H1 . 3 SI Boron Inject Recir Hydro 114E075 SI-02-H2 3 SI Boron Inject Surge Tank Hydro 114E075 SI-03-H1 ' SI Safety Inject Pmp Suction Head 114E075 SI-04-H1 2 SI RHR Pmp Suction F/Smps Hdro 114E075 SI-04-H2 2 SI Penetration #329 Guard Pipe, 114E075 Hydro SI-04-H3 2 SI Penetration #425 Guard Pipe Hydro SI-05-H1 2 SI SI Accumulators Hydro 114E075 SI-05-H2 2 SI N2 Line to Accumulator Hydro 114E075 SI-05-H3 2 NN PWR Operated Relief Vlv Bkup D-302-717 N2 SI-05-H4 2 NN Nitrogen Supply to SI Accumu- " 114E075 1stor Hydro SI-11-H1v r 1 SI Contmt Pressure Instrumentation D-302-241 SI-11-H2 1 . SI Contet Pressure Instrumentation D-302-242 SI-11-H3 1 SI Contat Pressure Instrumentation D-302-241 SI-11-H4 1 SI Contmt Pressure Instrumentation D-302-241 SP-01-H1 2 SP RB Spray Pump Suction Hydro D-302-661 SP-02-H1 2 SP RB Spray Rings Hydro D-302-661 SP-03-H1 2 SP RB Spray Discharge Hydro D-302-661 ; SP-04-H1 2 SP Penetration #327 Guard Pipe D-302-661 Hydro SP-04-H2 2 SP Penetration #328 Guard Pipe D-302-661 Hydro SP-05-H1 3 SP Caustic Addition Tank Hydro D-302-661 o r h . f b F C-9 (Rev. 2) [
i PSI HYDRO REFERENCE INDEX 3l
'i RJ . '
. CODE i PSI FILE # CLASS SYSTD1 DESCRIPTION FLOW DWG. ,
SS-01-H1 3 SS Primary Station Sauple Hydro D-302-771 SS-01-H2-~ 3 SS LPrimary Sampling'F/RCDT Hydro D-302-771 .
'SS-02-H1 2 SS Primary Sampling F/RHR Hydro- D-302-771' ;
SS-04-H1 2 SS Primary Sampling F/, Reactor Cool -D-302-771 SS-05-H1 2 SS Primary. Sampling F/ Accumulators D-302-771 i SS-06-H1 2 SS Primary Sampling F/Vol Cont Tank D-302-771 SS-07-H1 2 SS Primary Sampling F/Sem con D-302-771-Blowdown , SW-01-H1 3 SS WSW A Train Discharg#~ e D-302-222.
- SW-01-H2 3 SS WSW B Train. Discharge D-302-222 SW-01-H3 3 SW SW Pump A Discharge Hydro Test D-302.221 SW-01-H4 3 SW SW Pump B Discharge Hydro Test D-302:221
.N,.
( ~} _ y; SW-01-H5 3 SW SW Pump C Discharge Hydro Test D .302 -221 . SW-01-H6s.. e 3 SW "A' Train FS Supply Rdro . D-302-221 ; SW-01-H7' 3 . SW "B" Train FS Supply Hdro D-302-221 SW-01-H8 3 SW -FW 47 & 48 & Valve 3148-SW D-302-222 ,; Hydro j 11 SW-04-H1 2 SW SW A Train Hydro Test D-302-222 !! SW-04-H2 - 2 SW SW B Train Hydro Test D-302-222 it U VU-05-H1 3 VU Hydrotest Chilled Water Loop B D-302-841 'l f VU-06-H1 3 VU Hydrotest Chilled Water Loop A D-302-841 ! i WD-01-H1 3 WD Spent Resin Store Tank Supply 114E077 l
.h
' iM-02-H1 2 UD RC Drain Tank N2 Supply Hydro ll4E072 j WD-04-H1 2/3 WD RC Drain Tank Pump Piping Hydro 114E077 f
b m,.,: () il f e i . C-10 (Rev. 2) d
.. . ~ _ . . _ . _ , .__
. ,t 3l
~ '
- 1
~"
?? ' PSI' HYDRO REFERENCE INDEX I CODE. PSI" FILE #- . CLASS- . SYSTEM ~ DESCRIPTION FLOW DWG. I
'9D-06-H1' 3 WD Waste Holdup Tank-Hydro 114EflZ.2_. .f
. WD-06-H2: 3 . WD' Evaporate Feed Pump Piping '114E077 ;
WD-10-H1 3- WD' Waste Evap Hydro . 114E077' ! WD-12-H1~ 3 WD Spent Resin Storage Trans 114E077 '! Piping . .; l WD-13-H1 3 WD Spent Resin Storage Tank & 114E077 l Pump i t l i t
- n. ..
e t
- s. r . , ,
i
, }1 ;
fi a l
?
+ :
=
\I J
U ii l f I C-10A- (Rev. 2) _ . _ . c. . . . . . . . . ~ . .. . .. . ,_ ,. .__ . y
. . ~ . . , - . . . , . , . . - - -, ..-,., . . -, - . . . . , . ,
l . .
~
i SOUTH CAFOLINA ELECTRIC AND GAS COMPANY 1
! VIRGIL C. SUI 24ER NUCLEAR STATION t
PSI /ISI RESULTS DATA . ROUTING SHEET DATE ISSUED FOR REVIEW b S'" h [ DUE DATE $2"[b'b[ . f ORIGINATOR- - d Epeny- RETURN TO M Iv6*Er7- ;
.DEFCRIPTION: (PROCEDURE NUMBER, TITLE, PEVISION, REVISION DATE, ISSUED DATE)
Z> Gy - /0 - ,H/, 08ddxurs lOctwri Ls2tr* YES7 RW 0. V-l2-19 - i ,
//- 24/ -70 .
?
REVIEWED CATEGORY 'INIT/DATE .
-. ~
MAINTENANCE y %-?/
' SUPERVISOR A o r- 5-s.p/
', SCE&G 9 !
- INSPECTIOM f -
/
COORCINATOR SCE&G O TECHNICAL i-SUPPORT s
~
GER' t ANI l/E L - 3-5-P} _ PLEASE REVIETI THE ATTACHED HYDROSTATIC TEST RESULTS. 1 IF YOU CONCUR WITH THE RESULTS, PLEASE SIGN THE ATTACHED SIGNATURE ,! SHEET AND INITIAL AND DATE TRE ROUTING SHEET ABOVE. f I! n l h' , C-94 (Rev.'2)
-- --.._L... . , , ,, , ,
- - - - - - . . ~. . - _ _.. ,
. ??
06 VIRGIL C. SUMFMR NUCLEAR STATION PRESERVICE INSPECTION PROGRAM HYDROSTATIC TEST
. SYSTEM / SUBSYSTEM Di GGEL. C,edETzATDTz ! DC, J f O I
DATE: t~%C'8l *
- In accordance with subsection IWA-5210(b), of ASME Section XI, 1974 Edition, SCE&G' Company Nuclear Operations has witnessed /
reviewed the tests performed by'. ' Di~-i--\ D- Ol (Procedure No.) and accepts the.results as fulfilling Hydrostatic Test Requirements , for th'e above mentioned system / subsystem. APPROVAL / ACCEPTANCE: .
'7'
~
2f(7/ '- SCE&G INSPECTION COORDINATOR
/ / DATE f&2k]
Sf&&G TECH SUPPORT' GROUP Abd3:
' / DATE APPROVED: ji w ~
~' ~2-)r N[f ' .
MANAGER,' V. C. SUMMER FF f ACCEPTED: L ,-.-., A, kn} A N '
'2 '[T } '
AUTHORIZED NUCLEAR INSPECTOR DATE VCS FORM 152 (Rev. 1, 12/79) : C-95 (Rev. 2) l
. _ _ _ _ . _ - . - _ _ _ . . _ - . . . - - - . _ . _ _ _ . . _}}