ML20149J458

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Refuel 2 Inservice Insp Rept for 860419-871115
ML20149J458
Person / Time
Site: Callaway Ameren icon.png
Issue date: 02/12/1988
From:
UNION ELECTRIC CO.
To:
Shared Package
ML20149H950 List:
References
NUDOCS 8802230069
Download: ML20149J458 (8)


Text

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REFUEL 2 ,

INSERVICE INSPECTION SUNHARY i

for the E

UNION ELECTRIC [

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CALLAWAY PLANT  !

i Cal'1away Plant Union F,lectric Co.

P.O. Box 620 1901 Gratiot Street Fulton, MO 65251 St. Louis, MO 63166 t

Inspection Dates: Report Date:

April 19, 1986-November 15, 1987 February 12, 1988 4

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i EXAMINATIOP ABSTRACT for the CALLAk'AY RFFUEL 2 INSERVICE INSPECTION INTRODUCTICN This abstract presents an overview of the Inservice Inspections (ISI) perfereed during the period between Refuel I and Pefuel II at the Union Electric Callaway Plant. This abstract presents a rueber of items, included is the identification oft

- The organizatiens irvelved with ISI at Callaway and the specific responsibilities of each organization.

- The codes, Pegulatory Guides, and SUREGS used within the ISI.

- The specffic reports generated.

- The responsible inspection egency.

ORGANIZATION AFD,FESPONSIBILITIES l

The ISI at the Callaway Plant was accomplished by a number of organizations performing specific tasks. These organizations ard reepensibilities are listed below;

- Nuclear Frergy Services Incorporated (NES):

Responsibilitics; program development for the ISI of the reector l

vessel (RV) and the Balance of Plant (BOP),

L procedure develernent and oualification for l

the non-destructive examination (NDE) per-l forced by NES, and the perfornance of NDE on ,

i components not eyeeined by any other organiza- {

! tion.

- Combustion Engineering:

i Responsibilities t pregram development for the ultrasonic examinariers performed from the outside surface on the centrifuga11y cast and static i

cast materir.ls in the main loop piping and the Boron Injection Tank procedure develerrent and qualification, and the performance of 1

inspections.

.- _ - ,, . -__x . - - , .

- Union Electric Nuclear Operations Quality Control (UENO QC):

Responsibilitiest procedure development for the visual examinations defined in the NES BOP Program, the performance of the visual examinations defined in the NES BOP Program but not per-formed by others, and procedure development and inspection performance of selected BOP.

welds by liquid penetrant.

- Union Electric Nuclear Engineering Systems:

Responsibilitiest identification of welds to be inspected by NES, review of vendor procedures, and field supervision of NES. Westinghouse, and Combus-tion Engineering.

CODES ASME Section XI 1980 Edition. Winter 1981 Addenda was the governing Code for the performance of the inspections. This code year and addenda also applied to those components which were examined because of TSAR or Callaway Technical Specification requirements.

The codes used for component selection are as follows:

BOP Class 1 and 3 Piping: 1980 edition, Winter 1981 addenda BOP Class 2 Piping: 1974 edition. Summer 1975 addenda as required by 10 CFR 50.55a.

Reactor Vessel and Class 1. 2, and 3 components: 1980 edition, winter 1981 addenda REGULATORY GUIDES AND NUREGS The listing in this section presents the specific regulations used within the ISI of Callaway; U.S. Nuclear Regulatory Commission Standard Review Plan Sections 3-6-1 and 6.6 (NUREG-0800-1981).

U.S. Nuclear Regulatory Commission Regulatory Guide 1.26.

U.S. Nuclear Regulatory Commission Regulatory Guide 1.50.. 1

REFUEL II ISI REPORTS The results of the ISI at Callaway are compiled into two reports.

These are the Inservice Inspection Summary and the NIS-1 Data Report.

The ISI Summary is composed of a number of separate final reports or summaries. This is due to the number of erganizations that were involved with the Callaway ISI. The summary does not contain reports on the snubber inspections or eddy current inspections of the steam genera-tors since each has separate reporting requirements described in the callaway Technical Specifications. Each report was separately generated and then compiled into the Summary. The report or summary for Vendor activities also presents the procedures used, equipment used, personnel certifications, and equipment calibration records. This support information is not provided for UENO-QC activities since all such documents are permanently maintained by Union Electric. The particular volumes for each report are located at the Callaway Plant.

The NIS-1 Data Report presents the required information by refer-encing existing documents. These references are; the Retuel I ISI Summary, the Owner's N-3 Report, the Insta11er's N-5 Report, and the N-5  :

Addenda I. These references are also located at the Callaway Plant.

The Summary and the FIS-1 references are available for review upon recuest to the Manager, Union Electric Nuclear Engineering.

INSPECTION AGENCY The inspection agency responsible for the duties assigned by ASME fection XI for ISI is Hartford Steam Boiler Inspection and Insurance Company.

SUHMARY This Examination Abstract has been presented as the sole document describing the ISI performed between 18 April 1986 and 10 February 1987 at Callaway. Any questions concerning this abstract or the ISI program should be directed to the Manager, Union Electric Nuclear Engineering.

a -

GENERAL

SUMMARY

For The CALLAWAY REFUEL II INSERVICE INSPECTION INTRODUCTION This General Summary presents overall and significant results of the Refuel II ISI at the Callaway Plant. This summary has been generat-ed from other specific summaries or reports contained in the Refuel II ISI Summary. Specifics not identified in this summary are identified in the specific summaries or reports.

. CONDITIONS OBSERVED AND ACTIONS TAKEN Piping:

No degrading trends or rejectable indications were identified. The pipe inspections encompassed over 180 circumferential welds, 40 longitudinal welds, and 19 bolted connections. Over 420 ultrason-ic, dye penetrant, magnetic particle, and visual inspections were performed.

Components:

Steam Generators: No degrading trends or rejectable indications were identified on Steam Generators A and B. This encocpassed the examination of 4 shell welds, 1 feedwater nozzle weld, 24 support pad bolts, and 64 primary manway bolts. Over 100 ultrasonic, dye penetrant, and visual examinations were performed.

Pressurizer: No degrading trends or rejectable indications were identified. The inspections were identified. The inspections encompas' sed 2 shell welds, 3 spray nozzle welds, and one seismic lug attachment. Over 13 ultrasonic, magner.ic particle, and visual examinations were performed.

Residual Heat Removal Pump A: No degrading or rejectable indications

were identified. The inspections encompassed 1 nozzle wold and 3 support attachments. A total of 4 dye penetrant examinacions vere performed.

Boron Injection Tank: No degrading trends were identified. However, a rejectable surface indication was identified in an I-beam support attached to the tank. The indication was removed with minor grinding. The indication was evaluated to be an acceptable manufacturing surface blemish with no reportability required. An additional inspection was performed on a similar support and no indications were i

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identified. The inspections encompassed 2 scoport we.as and 1 circumferential tank weld. A total of 5 ultrasonic and dye pene-trant examinations-were performed.

Reactor Veasel: No degrading trends or rejectable indications were identified. The inspections encompassed: the inner radius of the 4 outlet nozzles; the 4 outlet nossles to vessel welds; 6 closure head welds; tha vessel to tiosure flange weld; 21 closure studs; 21 closure cuts; and 21 closure washars.

Over 120 ultrasonic magnetic particle, and visual inspections were performed.

Component and Piping Supporta:

No degrading trends or rejectabic indications identified. A total i

of 180 individual supports were visually inspected.

j Component and Piping Leakage: ,

No pressure retaining boundary leakage was identified. This encompassed over 350 visual inspections on hundreds of components and valves and thousan6s of feet of pipe.

CONCLUSION Refuel II ISI at Callaway encompassed more than 1,100 nondestruc-tive examinations. These examinations and those performed during Refuel

! I meet or exceed the minimum percentage of inspections required by ASME

< Section XI during the first 40 months (Period 1) of plant operation.

Welds and Components above the minimum percentages which were scheduled ,

for examination and defstred, will be performed at a later date as allowed by ASME Section XI. Relief Requests will be submitted for any

! welds or component which could not be examined as required by ASME Section XI.

As a result of the examinations performed and of the conditions found, there 1xists no general safety e-'cern for the pressure retaining integrity of plant safety systems.

I i l i ,

i REPAIR / REPLACEMENT ABSTRACT Fer The CALLAWAY PLANT INTRODUCTION This abstract pteserta 80 overview of the ASME Section XI Re-pair / Replacement activities perforced on ASME Class 1, 2 and 3 compo-nents and systems at the Callaway Plant. This abstract presents infor-ratien on the following items; Time period for which this abstract is applicable.

- Organizatione involved with repairs / replacements and specific i responsibiliticc.

- The ASPE Codes applied to repair /replacementa.

- The responsible inspection agency.

TIFF PERIOD This abstract applies to the tire period between refuel I conple-tion on 18 April 1986 and refuel II completion on 15 November 1987. t ORCANIZATIONS AND RESPONSIBILITIES ASME repair /replaeaments were perferred by various organizations -

that were assigned with certair restensibilities. These organizatiens and responsibilities are listed belev

- Unien Flectric Company (UE): L Responsibilities; establish a repsfr/ replacement program during construction and similarly f ar plant operation, ensure implemen-tation of the programs, review all contrt.ctor repair / replacement work perforced for Ca11cway, performance of repair /replacecent work after inicial construction, and certificatier. et all re-pair / replacement work. -

- Suppliers and Vendors l Respcnsibilities; perform repair / replacement work on equipment supplied to UE as requested by UE and allowed by particular nuclear authorizationc, crd perform repair / replacement work for UE under UE procedures.

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ASME CODES AND CODE CASES The performance of repair / replacement work at the Callaway Plan is performed to ASME Section XI. The 1980 edition, winter 1981 addenda of Section XI is the governing edition and addenda.

Code cases used are described in the Callaway Plant FSAR.

REPORTS Every ASME Section XI repair / replacement performed at Callaway has been reported on an NIS-2 Report. The use of the NIS-2 report is not l

required by the governing addenda of the Code. However Union Electric employs this method of reporting to provide additional review of re- '

pair / replacement activities to ensure code compliance.

A complete compilation of all repair / replacement activities per-formed at Callaway is documented in the N-5 Addenda II. This document has been generated for the period of time identified above and is part of the Refuel I Inservice Inspection Summary.

INSPECTION AGENCY The inspection agency responsible for the duties assigned by ASME Section XI for repair / replacement activities is Hartford Steam Boiler l

Inspection and Insurance Company.

SUMMARY

This Repair / Replacement Abstract has been presented as the sole document describing the repair / replacement activities performed at the Callaway Plant. Any questions concerning this abstract or the Section XI repair / replacement program in general should be directed to the Manager. Union Electric Nuclear Engineering.