ML20196C450
| ML20196C450 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 02/09/1988 |
| From: | FLORIDA POWER CORP. |
| To: | |
| Shared Package | |
| ML20196C403 | List: |
| References | |
| PROC-880209, NUDOCS 8802160104 | |
| Download: ML20196C450 (29) | |
Text
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INSERVICE INSPECTION OR'orida REPAIR AND REPLACEMENT PROGRAM p
Crystal River Unit 3 8'v'5SN 1
1 llEPAIR MG llEPLACBGli MiOGRM Review By:
//8me SI Section
'5 Approved By:
Nuclear Technical Support Superintendent 1
0
i i
.=
INSERVICE INSPECTION Florida Power REPAIR AND REPLACEMENT PROGRAM PAGE i OF Crystal River Unit 3 unscN 1
INDEX 2 AGE 1.0 Purpose 1
2.0 Scope 1
3.0 References 1
4.0 Definitions 3
5.0 Administrative Controls 7
6.0 General Program Requirements 8
7.0 Requirements for Section XI Repairs 9
7.1 General Repair Requirements 9
7.2 Repairs by Metal Removal 11 7.3 Repairs by Welding 12 7.4 Post-Repair Testing 14 7.5 Post-Repair Examination 14 7.6 Repair Records 15 8.0 Requirements for Section XI Replacements 15 8.1 General Replacement Requirements 15 8.2 Post Replacement Testing and Examination 17 8.3 Repair Records 18 9.0 Requirements for Records and Reports 18 10.0 Attachments 20
-i-11 64 912 903
INSERVICE INSPECTION
@ Florida REPAIR AND REPLACEMENT PROGRAM Power PAGE 11 OF Crystal River Unit 3 1
.s y,3,o s LIST OF CHANGED PAGES ES REVISION NO.
Dyf2 All pages revised 1
02/09/S8 ii 11 $4 912 9C2
INSERVICE INSPECTION Florida
(
Po.. w..e. r REPAIR AND REPLACEMENT PROGRAM PAGE 1
OF 26 s
Crystal River Unit 3 l ams.o=
1 1.0 PURPOSE 1.1 This program defines the scope and content of ASME Section XI repair and replacement activities to ASME defined Class 1,
2, and 3,
components and component supports; Class MC pressure retaining components and their integral attachments; and steel portions of Class CC pressure retaining components not backed up by concrete and their integral attachments at Crystal River Unit 3.
1.2 To adequately define the scope and content this program includes subparts on references, and definitions.
2.0 SQPI 2.1 10 CFR 50.55a requires use of ASME Section XI rules to develop a program detailing requirements of the complete repair cycle for all repairs to the pressure retaining boundary of ASME Code Class 1, 2, 3,
components and their supports.
This program sets forth the l
requirements for all Section XI repair and replacement activities, and includes ASME Code Class MC and certain CC components.
l 2.2 Repairs and replacements performed in accordance with this program will implement the requirements of ASME Section XI, 1983 Edition through Summer 1983 Addenda.
3.0 REFERENCES
3.1 ASME Section XI, Rules for Inservice Inspection of Nuclear power plant Components, 1983 Edition through Summer 1983 Addenda etz ee:
INSERVICE INSPECTION 8MM REPAIR AND REPLACEMENT PROGRAM kk,(
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OF gg Crystal River Unit 3 "v'5CN i
3.2 ASME Section IX, Welding and Brazing Qualifications 3.3 ASME Section V, Nondestructive Examinations 3.4 ASME Section III, Nuclear, Power Plant Cokponents, as accepted by the NRC as listed in 10 CFR 50.55a(b)(1).
3.5 ASNT-TC-1A, 1980, Recommended Practice 3.6 ANSI-N45.2.6 - 1973, Qualifications of Inspection, Examination and Testing Personnel for Nuclear Power Plants 3.7 MTAP-06, Certification of NDE Personnel, Procedures, and Contractors in Accordance with ASNT-TC-1A and AWS 3.8 MTAP-07, certifications of NDE Personnel, Procedures and Contractors in Accordance with ANSI N45.2.6 and Section XI l
3.9 Nuclear Operations Welding (NOW) Manual 3.10 NOD-05
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INSERVICE INSPECTION
@ Florida REPAIR AND REPLACEMENT PROGRAM f
PAGE 3
OF 26 Crystal River Unit 3 ar. ism 1
4.0 DEFINITIONS
4.1 ADourtenance
an item intended to be attached to a completed and l
stamped component which has work performed on it requiring l
verification by an inspector (ANII).
l 4.2 Authorized Nuclear Inspector ANI:
an inspector employed by an Authorized Inspection Agency who is qualified for Division 1 or Division 2 construction inspection by ANSI N626.0 - 1974 or ANSI N626.2 - 1976 respectively.
4.3 Authorized Nuclear Inservice Inspector (ANII):
an inspector employed by an Authorized Inspection Agency who is qualified to monitor activities for compliance with ASME Section XI by ANSI N626.1 - 1975.
4.4 Code-Stamped
The presence o* a physical stamp (N, NA, NPT, NV, or U) which indicates that a component or part has been constructed to the requirements of Section III or Section VIII.
4.5 Component
An item in a nuclear power plant including vessels, piping systems, pumps, valver, heat exchangers, tanks, core support structure and component supports.
4-INSERVICE INSPECTION 8 Florida REPAIR AND REPLACEMENT PROGRAM Po..,w..enr
,,oc 4
or 2s u
Crystal River Unit 3 meme 1
4.6 Component Sucoort:
Component supports encompass those structural l
elements relied upon to either support the weight of or provide j
structural stability to components and piping.
These metal supports j
that are designed to transmit loads from the component and piping to the load carrying building or foundation structures.
This shall include the attachment portion of intervening element (s) to pressure retaining components, integral and non-integral attachments of pressure retaining components, and integral and non-integral supports.
l 4.7 pipina System:
A functional nuclear power plant system with bounda-ries defined by a plant Design Specification, and/or System Flow Diagrams.
4.8 Flaw Indication:
Denotes the evidence or signal obtained by l
application of non-destructive examination that may reveal the l
presence of a flaw, or surface degradation.
Flaws include cracks, inclusions, aligned or clustered rounded indications, lack of weld penetration or fusion, and laminations, or combinations thereof.
l 4.9 Repair Oroanization:
An organization that Icpairs or replaces components or systems under the provisions of this program.
Either FpC or an outside vendor, provided the requirements of 7.10.5 are satisfied, may be the repair organization.
4.10 Repair:
The activity in which unacceptable flaw indications are removed or reduced to an acceptable limit by thermal cutting, or mechanical methods (machining or grinding) and/or replacing removed metal, if required, with weld metal according to the rules of Section XI.
There may be repairs where no material is removed.
A
o INSERVICE INSPECTION
@ Florida REPAIR AND REPLACEMENT PROGRAN Po. o..e. nwr eroe s
or 2s cc.
Crystal River Unit 3 afv'ScN 1
repair does not necessarily require the addition of weld metal.
Repair may involve plugging heat exchanger tubes.
The scope of l
applicability as defined in IWA-4110 includes all ASME Code Class 1, l
2, 3, MC, and CC pressure retaining boundaries, components and their l
supports, welding appurtenances, subassemblies and core support l
structure.
l 4.11 Replacement:
The activity in which a component, appurtenance, or pressure-retaining subassembly or part of a component or system is removed and replaced by an identical or substitute item or the same is added or modified.
Installation of new parts or components to l
existing systems where there is no pre-existing part is considered a replacement (this includes attachment of nonpressure retaining parts welded to the pressure boundary of components).
It also includes syctem changes such as rerouting of piping within the scope of Section XI.
It does not include the addition of complete new systems.
(New systems are addressed by Section III.)
4.12 Oriainal Construction Code:
The original Code (s) Edition and Addenda under which the component was constructed and installed.
INSERVICE INSPECTION 9NM REPAIR AND REPLACEMENT PROGRAM
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OF 26 Crystal River Unit 3 namm 1
4.13 Repair / Replacement Code:
The construction or Section XI code (s) l Edition and Addenda to be used for the repair or for the construction of the replacement component / subassembly /part.
This may be the same as the Original Construction Code or it may be a later Edition and Addenda, in part or whole.
It may also be Section III of the ASME Code, in part or in whole.
This is the Code identified on line Sa of form NIS-2.
All Code Cases used in conjunction with that repair or replacement must also be identified on form NIS-2.
4.14 Examination:
Shall denote the performance of nondestructive testing and visual observation such as volumetric examinations (radiography, ultrasonic and eddy current), surface examinations (liquid penetrant or magnetic particle), and visual examinations (VT1, VT2, VT3, and VT4).
4.15 Construction / Constructed:
Use of the words ' construction" and "constructed" include rules for materials, design, fabrication, examination, and testing.
More than one Code may be applicable to the "construction' of the system or component.
I 4.16 Core Support Structure:
Those structures or parts of structures i
l l
which are designed to provide direct support or restraint of the 1
core (fuel and blanket assemblies) within the reactor pressure
]
vessel.1 i
1 Article NCA-9000,Section III, ASME Boiler & pressure vessel Code, 1986 Edition.
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INSERVICE INSPECTION 8MM REPAIR AND REPLACEMENT PROGRAM
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PAGE 7
OF 26 Crystal River Unit 3 REYl$CN 1
5.0 ADMINISTRATIVE CONTROLS l
5.1 The Nuclear Technical Support Superintendent (NTSS) is the focal l
point for implementation and control of this program.
The Nuclear l
Technical Support Superintendent provides interpretations of this l
l program and assures the administrative controls for changes are implemented as described below.
l l
5.2 procedures implementing this program include poQAM procedures, l
Engineering procedures, and ISI Administrative procedures, but is l
not limited to these types of procedures.
In addition to the j
specific procedure's administrative controls, procedure changes are l
evaluated to identify any new or revised relief requests and any l
resultant changes to this program document.
Tf the proposed l
procedure change requires a Relief Request, the change shall not be j
implemented until NRC approval is received.
If the proposed l
procedure change causes a change to this program document, then the l
procedure change shall not be implemented until the NTSS or his l
designee has approved the program change.
INSE3VICE INSPECTION Florida
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g REPAIR AND REPLACEMENT PROGRAM PAGE 8
oF 26 Crystal River Unit 3 Wme 5.3 In general, changes to this program shall be evaluated to l
identify new or revised relief reguests.
Non-relief request l
changes to this program shall be reviewed by the interfacing l
departments and approved by NTSS or his designed prior to l
implementation.
Changes to the program that do not require a l
Relief Request may be implemented following interfacing l
department reviews and NTSS approval above provided the changes j
are included in the next annual update of the program to the NRC.
l l
5.4 Annually, changes to this program made within the prior 13 l
months, excluding 30 days prior to the submittal, shall be j
subr.itted to the NRC.
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6.0 CENERAL PROGRAM REOUIREMENTS 6.1 Unless the repair or replacement is exempted by this program, the ANII shall be notified prior to starting any welded repair or welded replacement, and shall be kept informed of the progress of l
work so that necessary inspections can be performed.
6.2 ASME Code Cases used in conjunction with repairs or replacements l
will be noted on the NIS-2 Form, Attachment 1 to this program, l
which is part of the documentation for the repair.
For Section l
XI related Code Cases, only Code Cases which have been proved l
for FpC by the NRC may be used at CR-3.
For Section III related l
Code Cases, only those listed in Regulatory Guide 1.84 and 1.85 l
may be used without NRC specific approval.
Specific NRC approval l
is required prior to use of Section III Code Cases not in R. G.
l 1.84 and 1.85.
l nu e, x,
INSERVICE INSPECTION Florida
,, Power REPAIR AND REPLACEMENT PROGRAM Crystal River Unit 3 eso i
6.3 This Repair and Replacement Program shall be subject to review by the NRC and the ANII.
6.4 Nondestructive examinations shall be performed by personnel quali-fied through Material Technology Administrative procedures.
6.5 The Repair / Replacement Codes, including rules for design, materials, \\
fabrication, procurement, erection, and installation shall be iden-tified by Nuclear Operations Engineering.
6.6 ASME Section XI allows the use of later editions of the original Construction Code or Section III of the ASME Code, in part or in '
whole, provided the criteria of Section 7.10.6 and 8.2 of the pro-gram are satisfied.
6.7 Routine servicing and maintenance to pumps and valves will be per " l formed in accordance with plant maintenance procedures.
In addi-l tion, to those items defined IWp-2100(e) and IWV-2300(d), routine l service and maintenance to ASME Class 1,
2, 3, and MC Comporants, l such as, removing cuts, burrs, scratches, nicks, pits, and score l marks in gasxet surfaces, valve seats / disc, bearing housing, andl 8
sealhousings,willbeperformedinaccordancewithCR-3 maintenance l procedures.
These activities involve metal removal and will bel documented in the CR-3 Work package.
Thesetypeactivitieswouldbel limited to localized areas and the amount of material removed would l be minimized so that the structural integrity of the pressure boun-l dary is not compromised.
Thcse routine service and maintenance l activities would be exempt from IWA-4000.
l 7.0 REOUIREMENTS FOR SECTION II REPAIES 7.1 f,ENERAL REPAIR REOUIREMENTS 7.1.1 This section sets forth the rules and requirements for repair activities, where the word repair is defined in paragraph 4.10.
7.1.2 The scope of applicability is defined in IWA-4110 as including all ASME Code Class 1,
2, 3,
MC, and certain CC pressure retaining l boundaries, components and their supports, including appurtenances and subassemblies and core support structures.
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INSERVICE INSPECTION OM REPAIR AND REPLACEMENT PROGRAM I
PAGE 10 OF 26 Crystal River Unit 3 umow i
7.1.3 The repairs shall be performed in accordance with the Repair Code, as defined in paragraph 4.13.
If the repair cannot be performed in accordance with these requirements then the following may be used:-
a.
IWB-4000 for Class 1 craponents b.
IWC-4000 for Class 2 components c.
IWD-4000 for class 3 components d.
IWE-4000 for Class MC components 7.1.4 Flaw indications resulting frem ASME Section XI inspaction of components or component supports shall be acceptable by one of the four techniques below:
a.
Acceptance by Examination b.
Acceptance by Evaluati.on c.
Acceptance by Repair d.
Acceptance by Replacement 7.1.5 The rules for items a and b, Acceptance by Examination and by Evalu-ation, are contained in the Examination program Plan.
If through that program it is determined that a repair is necessary, then the rules of this program apply.
INSERVICE INSPECTION Florida Power REPAIR AND REPLACEMENT PROGRAM PAGE 11 OF 26 Crystal River Unit 3 an'sc~
1 7.1.6 The rules for this program apply to welded replacements ne C&tter why the replacement is being made.
The rules foi replacements are given in Section 8.0 of this program.
7.1.7 The Section XI code repair requirements for Class MC components were in the course of preparation when the 1983 addenda were issued.
If metal removal and welding are required on Class MC components a work package will be prepared that specifies the requirements in accord-ance with the original design and constraction codes.
Later 1
l editions of the Construction code or section III, either in its entirety or portions thereof may be used.
l 7.1.8 The Section XI Code repair requirements for Subsection IWF were in the course of preparation when the 1983 Edition and Summer 1983 addenda were issued.
The supports shall be repaired in accordance with the requirements of the original design and t;nstruction codes.
Later editioas of the construction Code or Section III, either in its entirety or portions thereof, may be issued.
7.2 REPAIRS BY METAL REMOVAL 7.2.1 Not all repairs require the addition of weld filler metal.
For all repairs the excavation that removed the flaw shall be processed as outlined in the following steps, 7.2.2 through 7.2.7.
7.2.2 A reference point shall be established from which the excavation can l
be dimensionally located, during and after the repair.
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INSERVICE INSPECTION
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REI' AIR AND REpLACET.ENT PROGRAM PAGE 12 OF 26 Crystal River Unit 3 qvise 1
7.2.3 The methods, thermal and/or mechanical, utilized in the flaw excava-tion shall be documented.
7.2.4 The size of the cavity excavated and the method of measurement shall be documented.
7.2.5 Following the final grinding, the excavatir surface shall be examined by magnetic particle or liquid penetrant method to ensure that the flaw indication does no longer exceed the applicable NDE acceptance standard.
7.2.6 Indications detected as a result of the excavation, per the instrce-tions of 7.2.5 above, that are not associated with the flaw being l
removed shall be evaluated against the applicable NDE acceptance standard.
7.2.7 For those excavations where no repair Welding is planned, ult.asonic or mechanical thickness measurements shall be performed to verify that the required wall thickness has been maintained.
7.3 3EPAIR3 BY WELDING 7.3.1 prior to any repairs by welding being authorized, an evaluation of the suitability of the welding procedure to be used shall be performed.
If the repair is due to f ailu'.e, the cause of the failure should be considered in the evaluat'.on.
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INSERVICE INSPECTION 9M REPAIR AND REP W EMENT PROGRAM Po., w..e,,r, PAGE 13 0F 26 v
2 Crystal River Unit 3 mv:sca i
7.3.2 All welding procedures shall be qualified in accordance with kSME Section IX.
7.3.3 All wclders shall be qualified in acecrdance with ASME Section IX.
7.3.4 Any additional requirements of ASME Section XI or the Repair / Replacement Code that impact the qualification of welders or welding procedures shall be identified in the "Nuclear Operations l
Welding Manual" (NOW, reference 3.9).
Welding procedures and welders need not be qualified to Sectir.,n III, unlessSection III is l
used as the Repair Code.
l 7.3.5 Welders need not be employed directly by Repair Oraanization, whether the Repair Organization is Florida Power Corporation or a contracted company, provided that these welders work under the Quality Assurance Program of the Repair Organization.
This program shall include the following:
7.3.5.1 Requirements for the complete and exclusive administration and tech-nical supervidion of all welders by the Repair Organization.
7.3.5.2 Requirements for contractual control which provides the necessary authority to assign and remove welders at the discretion of the Repair Organization.
7.3.5.3 Documentation that the Repair Organizations Qualit*, Assurance Pro-gram is acceptable to Florida Power Corporations ANII.
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O e
INSERVICE INSPECTION Florida REPAIR AND REPLACEMENT PROGRAM power PAGE 14 OF 26 Crystal River Unit 3 aanscN 1
7.3.6 Where repair welding to the requirements of the original l
Construction Code or Section III is impractical, the weld repair l
techniques of Section XI and when post Welo Heat Treatment is not l
performed in accordance with the Original Construction Code, l
subarticles IWB-4300, IWC-4300, and IWD-4300 nay be utilized.
Qualification of the techniques in accordance with ASME Section IX, as modified in the subarticles IWB-4300, IWC-4300, and IWD-4300, SHALL be performed PRIOR to using them.
7.4 p0ST-REPAIR TESTING 7.4.1 Following repairs by welding on the pressure retaining boundary a system hydrostatic test SHALL be performed in accordance with IWA-5000.
l 7.4.2 Hydrostatic testing need not be performed on those items that are specifically exempted by Section XI in subarticle IWA-4000 and IWA-5000.
7.4.3 A pressure test to Repair / Replacement Code specifications may be l
performed at the discretion of Nuclear Operations Engineering, but l
is not required.
l 7.5 p0ST-REPAIR EXAMINATION 7.5.1 Following repairs, the repaired area SHALL be examined to establish a new preservice record.
na sum
INSERVICE INSPECTION Florida i
f Power REPAIR AND REPLACEMENT PROGRAM PAGE 15 OF 26 Crystal River Unit 3 S'5 CN 7.5.2 The examination SHALL include the method that detected the flaw for repairs initiated to remove or correct flaws.
7.5.3 The preservice record SHALL include the preservice examination requirements of IWX-2000.
This requirement is in addition to the l
Repair / Replacement Code NDE requirement.
l 7.5.4 If the repair includes the complete isolation of the item bearing the flaw, such as heat exchanger tube plugging, then the require-ments of step 7.5.1 above SHALL NOT APPLY.
7.6 REPAIR RECORDS 7.6.1 A copy of form NIS-2, to this program, SHALL be completed for every repair.
8.0 REOUInD(ENTS FOR SECTION XI REPLACEMENTS 8.1 General Replacement Recuirements 8.1.1 This section sets forth the rules and requirements for replacements, where the word replacement is defined in paragraph 4.11, 8.1.2 Replacements may meet all or portions of the requirenents of later editions of the original Construction Code, provided that the following requirements are met, w
s,2 w2
INSERVICE INSPECTION 8NM REPAIR AND REPLACEMENT PROGRAM bI, f$(
PAGE 16 OF 26 Crystal River Unit 3 arvisen i
8.1.2.1 The requirements affecting the design, fabrication, and examination of the replacement are reconciled with the Owner's Specification.
8.1.2.2 Mechanical interfaces, fits and tolerances that provide satist'actory performance are not changed by the later edition of the Original l
Construction Code.
8.1.2.3 Modified or altered designs are reconciled with the owner's Specifi-cation through the Stress Analysis Report, Design Report, or other suitable method which demonstrates the satisfactory use for the specified design and operating conditions, whichever is applicable.
8.1.2.4 Materials are compatible with the installation and system require-ments.
8.1.3 prior to authorizing the installation of a replacement an evaluation of the suitability shall be performed.
8.1.3.1 If the replacement is due to failure, the evaluation shall consider cause(s) of f ailure to ensure that the selected replacement is suit-able.
8.1.3.2 The replacement evaluation report shall be transmitted to Nuclear plant Quality Document Files.
t INSERVICE INSPECTION 9NM REPAIR AND REPLACEMENT PROGRAM
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PAGE 17 OF 26 Crystal River Unit 3 aEWON 1
8.1.4 All replacements involving welding shall comply with the Repair program requirements, Section 7.0 of this document.
8.1.5 The following items shall be exempt from the replacement program requirements:
a.
gaskets b.
instruments c.
electrical conductors and insulators d.
piping, valves and fittings that are 1 inch nominal pipe size or less, except for material and primary strers levels.
l e,
nonstructural pump and valve internals, except when the original equipment was constructed in accordance with a Construction Code or Code Case, f.
pump seal package and valve packing
'3. 2 POST-REPLACEMENT TESTING AND EXAMINATION l
8.2.1 Following replacements affecting the pressure retaining boundary, a l
system pressure test SHALL be performed in accordance with IWA-5000.
l 8.2.2 pressure testing need not be performed on those items that are l
specifically exempted by Section XI in subarticle IWA-7000 and l
8.2.3 A pressure test to construction code specifications may be performed l
at the discretion of Nuclear Operations Engineering, but is not
{
required.
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INSERVICE INSPZCTION M
REPAIR AND REPLACEMENT PROGRAM
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PAGE 18 OF 26 Crystal River Unit 3 memon 1
8.2.4 Prior to return of the plant to service, a preservice inspection shall be made in accordance with IWX-2000.
l 8.3 RFgAIR RECORDS 8.3.1 A copy of form NIS-2, Attachment. 1 to this program, shall be completed for each item replaced by this program.
10 REOUIREMENTS FOR RECORDS AND REPORTS 9.1 A copy of form NIS-2, Attachment i' to this program, SHALL be completed for every repair and replacement.
9.2 The following steps are instructions for completing the form NIS-2:
9.2.1 Line 1 is completed by Nuclear Operations Engineering as follows:
l FLORIDA POWER CORPORATION P.O. Box 14042 St. petersburg, FL 33733
)
9.2.2 Line 2 is completed by tiuclear Operations Engineering as follows:
l l
4 CRYSTAL RIVER UNIT 3 P.O. Box 1240 Crystal River, FL 32629
~
t INSERVICE INSPECTION 8M REPAIR AND REPLACEMENT PROGRAM h!
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PAGE 19 OF 26 Crystal River Unit 3 ansow 1
9.2.3 Line 3 is completed by Nuclear Operations Engineering with the name l
and address of the repair organization, the purchase order number, job number, work request number, et cetera, as appropriate.
9.2.4 Line 4 is completed by Nuclear Operations Engineering with the
[
system identification.
9.2.5 a.
Line 5a is completed by Nuclear Operations Engineering with the l
Repair / Replacement coda edition, addenda, and the Code Cases utilized.
b.
Line 5b is completed by the ISI Specialist.
9.2.6 Line 6 is completed by Nuclear Operations Engineering.
9.2.7 Line 7 is completed by Nuclear Operations Engineering.
l 9.2.8 Line 8 is completed by the ISI Specialist.
9.2.9 Line 9 is completed by Nuclear Operations Engineering.
l 9.3 It shall be the responsibility of the ISI Spectalists to sign the
' Certificate of Compliance
- section of form NIS-2 and the then main-tain the form until the ANII has signed it.
9.4 The ISI Specialists shall review the work packages suf ficiently to attest that the repair complies with Section XI.
t INSFRVICF, INSPECTION REPAIR AND REPLACEMENT PROGRAM p
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Crystal River Unit 3 MVISCN 1
9.5 Forn NIS-2 for all repurs and replaccaents performed since the l
previcos refuellny, shall be submitted with the Summary Report and form NIS-1 that is fi39d after the next scheduled refueling outage.
9.6 A copy of the Summary Report submission is transmitted to Nuclear Plant Ouslity Document Files.
No other copy of form NIS-2 need be trancet(tod.
10.0 JITACHMENTE 10.1 ATTACR*iENT 1, FORM NIS-2 10.2 A*fTAfl! MENT 2, Procedure Cross Reference List l
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INSERVICE INSPECTION
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PAGE 21 OF 26 Crystal River Unit 3 REVISCN 1
ATTACIBtENT 1 FORM MIS-2 OWNER'S REFORT OF REPAIR OR REPLACDIEriT AS REQUIRED BY THE PROVISIONS OF ASME CODE SECTION XI 1.
Owner Florida Power Corporation Date
( Na.Te )
P.O.
Box 14042 St. Petersburo. FL 33733 Sheet of (Address) 2.
Plant Crystal River Unit 3
(Name)
P.O.
Box 1240 Crystal River. FL 32629 (Address) 3.
Work Performed By (Name)
(Repair Org. P.O. No.,
Job No., etc.)
(Address) 4.
Identification of System 5.
(a) Applicable Construction Code 19
- Edition, Addenda Code Cases l
(b) Applicable Edition of Section XI Utilized for Repairs or Replacements Addenda, Code Cases
- 6. Identification of Components Repairs or Replaced and Replacement Components.
' Name of Name of Mfrs. Ser.
Nat'l Other Year Repaired ASME Code Component Mtr.
No.
Bd.No.
Identi-Built Replaced Stamped fication or (Yes or No)
Replacement 1
. \\ o INSERVICE INSEECTION
@ Florida REPAIR AND REPLACEMENT PROGRAM h,}
PAGE 22 OF 26 Crystal River Unit 3 aemos 1
ATTACHMENT 1 (Continued)
FORM NIS Continuation 7.
Description of Work 8.
Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other Pressure psi Tests Temp.
- F 9.
Remarks (Include P. O. Number) l CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and this conforms to Section XI of the ASM.? Code.
(repair or replacement)
Signed 19 (0 wrier or Owner's Designee)
Title Date CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued py the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of employed by of have inspected the (Repairs or Replacements) described in this Report on 19
, and state that to the best of my knowledge and belief, this repair or replacement has been constructed in accordance with Section XI of the ASME Code.
By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement in this Report.
)
FurLhermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
Date Caumissions (State or Province, National Board)
I
. s.
INSERVICE INSPECTION 8 Florida REPAIR tsND REPLACEMENT PROGRAM PAGE 23 op 26 Crystal River Unit 3 avision 1
ATTACIMENT 1 (Continued)
NOTE: Supplem<!ntal sheets in form of lists, sketches, or drawings may be used provided (1) size is 8-h in. x 11 in.(2) information in Items 1 through 6 on this data report is included on each sheet and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
Owner or Owner's designee and the ANII shall sign at the bottom of each supplemental sheet.
INSTRUCTIONS The item numbers below currespond to the block numbers on the ' Form NIS-2, Owner's Report of Repair or Replacement," Attachment 1.
1)
Enter Owner's name and address:
Florida Power Corporation P.O. Box 14042 St. Petersburg, FL 33733 2)
Enter Plant name and address:
Crystal River Unit 3 P.O. Box 1240 Crystal River, FL 32629 3)
.nter the name and address of who perforired the work, Florida Power corporation, P.O.
Box 1/042, St. Petersburg, FL 33733, and the Purchase O r d e't, Job Number, Work Request Number, etc.
4)
Enter identification of system (e.g., Chemical and Volume Control System).
5) a)
Enter applicable Repair / Replacement Code (s)
(e.g.,
Section III, 74 l
Edition, S'75 Addenda, N/A for not applicable, or the number of the Code Case (s) used.)
b) Enter applictble Edition of Section l'.I Utilized for Repairs or Replacements (e.g., 83 Addenda S83 and any Code Cases used).
6)
Enter identification of components repaired or replaced and replacement components.
Examples are as follows:
Name of Components:
2*S.S. Globe Valve Name of Manufacturers:
Kerotest Mfrs. Serial Number:
CAQ 12-4 National Board Numbers:
N/A for not applicable or the desig-nated National Board Number if assigned.
Other Identification:
(Valve ID Nunber)
Year Built:
1974 Repaired, Replaced, or Replacement:
Repaired ASME Code Stamped (Yes or No):
No
a *, s INSERVICE INSPECTION
@ Florida REPAIR AND REPLACEMENT PROGRAM PAGE 24 OF 26 c
Crystal River Unit 3 arvision 1
- 7) Enter description of work (e.g.,
drilled eight (8) holes through lip of valve to facilitate installation of limit switch and locking device).
- 8) Enter tests conducted (e.g.,
mark the appropriate block, ' Hydrostatic",
' Pneumatic", "Nominal Operating Pressure', or 'Other'.
Include the test pressure and temperature; in the case of "Other" being marked, specify the test, like PT for liquid penetrant testing, etc.)
- 9) Enter remarks (e.g.,
See attached NpV-1 form).
P.O.
numbers provide traceability to the manufacturer date reports.
In the "Certificate of Compliance" section, enter the work repair if a Iepair was done, or replacement if the item was replaced.
This section will be signed by the owner or his designee along with title and date.
In the ' Certificate of Inspection" section, the designated inspection agency will complete this part of the form.
INSERVICE INSPECTION I9.e Florida REPAIR AND REPLACEMENT PROGRAM Po. w..er PAGE 25 OF 26 s
Crystal River Unit 3 aavisos 1
ATTACHMENT 2 IMPLEMENTING PROCEDURE CROSS REFERENCE IMPLEMENTING RESPONSIBLE PROGRAM STEP PROCEDURE ORGANIZATION 6.1 CP-113 NOM /MAINT. PLANNERS 6.2 ISISM ISI 6.3 ISISM ISI 6.4 MTAP MAT'L TECH 6.5 SREP NUC OPS ENG 6.6 SREP NUC OPS ENG 7.1.1 NONE N/A 7.1.2 NONE N/A 7.1.3 CP-113 NUC OPS ENG 7.1.4 ISISM ISI 7.1.5 ISISM ISI 7.1.6 NONE N/A 7.1.7 SREP NUC OPS EhG 7.1.8 SREP NUC OPS ENG 7.2.1 NONE N/A 7.2.2 NOW NUC WELDING ENG 7.2.3 NOW NUC WELDING ENG 7.2.4 NOW NUC WELDING ENG 7.2.5 ISISM ISI 7.2.6 ISISM ISI 7.2.7 ISISM ISI 7.3.1 SREP NUC OPS ENG./NUC WELDING ENG l
7.3.2 NOW NUC WELDING ENG 7.3.3 NOW NUC WELDING ENG 7.3.4 NOW NUC WELDING ENG 4
7.3.5 NOW NUC WELDING ENG 7.3.5.1 NOW NUC PROCUREMENT 7.3.5.2 NOW NUC PROCUREMENT 7.3.5.3 NOW NUC PROCUREMENT 7.3.6 NOW NUC WELDING ENG 7.4.1 SP-210 ISI 7.4.2 SP-210 ISI 7.4.3 SREP NUC OPS ENG 11 S4 912 9C2
e *..
INSERVICE INSPECTION i
{
er REPAIR AND REPLACEMENT PROGRAM PAGE 26 OF 26 Crystal River Unit 3 aeviseu 1
ATTACHMENT 2 (Cont'd)
IMPLEMENTING PROCEDURE CROSS REFERENCE IMPLEMENTING.
RESPONSIBLE PROGRAM STEP PROCEDURE ORGANIZATION 7.5.1 ISISM ISI 7.5.2 ISISM ISI 7.5.3 ISISM ISI 7.5.4 NONE N/A 7.6.1 SREP NUC OPS ENG/ISI l
ISISM ISI 8.1.1 NONE N/A 8.1.2.1 SREP NUC OPS ENG.
8.1.2.2 SREP NUC OPS ENG.
8.1.2.3 SREP NUC OPS ENG.
8.1.2.4 SREP NUC OPS ENG.
8.1.3 SREP NUC OPS ENG.
8.1.3.1 SREP NUC OPS ENG.
l 8.1.3.2 SREP/CP-113 NUC OPS ENG./MAINT 8.1.4 NONE N/A 8.1.5 SREP NUC OPS ENG.
8.2.4 ISISM ISI 8.3.1 SREP/ISISM NUC OPS ENG./ISI 9.1 SREP NUC OPS ENG./ISI 9.2 SREP NUC OPS ENG./ISI 9.3 ISISM ISI 9.4 ISISM ISI 9.5 ISISM ISI 9.6 ISISM ISI 134 s12 *a2