ML20080K150

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Suppl 1 to Response to NRC Draft Technical Evaluation Rept for Waterford 3 Ses on Control of Heavy Loads
ML20080K150
Person / Time
Site: Waterford Entergy icon.png
Issue date: 11/30/1983
From:
LOUISIANA POWER & LIGHT CO.
To:
Shared Package
ML20080K143 List:
References
REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR NUDOCS 8402150313
Download: ML20080K150 (9)
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4-4 LOUISIANA POWER & LIGHT COMPANY WATERFORD SES UNIT NC, 3' RESPONSE TO NRC DRAFT - TECHNICAL EVALUATION REPORT (TER) FOR WATERFORD 3 SES ON' CONTROL OF HEAVY LOADS SUPPLEMENT NO. 1 a.

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I November 1983 8402150313 840209 PDR ADOCK 05000392 i E- -PDR

CONTENTS P_a ge

1.0 INTRODUCTION

1

'2.0 REACTOR VESSEL (CLOSURE) HEAD LIFTING RIG 1 3.0 TABLE NO. 1 6 SDD%RY OF STRESS LEVELS AND SAFETY FACTORS IN HEAD LIFT R1G C0!!PONENTS ATTACHMENT:

' Figure III - Lifting Rig to Closure Head i

4

1.0 INTRODUCTION

Pu rsua nt to our commi tment in our " Response to NRC Draft - Technical Evaluation Report (TER) for Waterford 3 SES on Control of Heavy Loads dated January 1983" to submit a compliance evaluation for the Reactor Vessel (Closure) Head Lift Rig when review is completed by the rig vendor, we are now herein submitting the results of our evaluation in this Supplement No. 1.

We have evaluated the lift rig design and fabrication for compliance with Guideline 4 - Special Lif ting Devices, [NUREG-0612, Article 5.1.1(4)] and the associated requirements of _ ANSI N14.6-1978.

P 2.0 REACTOR VESSEL (CLOSURE) HEAD LIFTING RIC This rig is listed as Item No. I of Section 6.0 in the " Response to NRC Drsft - Technical Evaluation Report (TER) for Waterford 3 SES on Control of Heavy Loads dated January 1983."

A stress summary for the rig using static plus dynamic loads are shown on Table 1 (Page 6).

The following tabulation lists the Section Referenced and the degree of compliance for the above-listed rig.

ANSI N14.6-1978 Reactor Vessel (Closure)

Section Referenced Head Lift Rig Section 3.1 3.1.1 Limitations on the use of lif ting Used only for the RV closure devices head and the cavity seal plate 3.1.2 Identification of critical compon- All lif ting components are ents and definition of critical considered critical. See characte ristics Table 1 (Page 6) for listing.

3.1.3 Signed stress analyses, demonstrating Safety margins demonstrated on appropriate margins of safety Table 1 (Page 6) 3.1.4 Indication of permissible repair Repairs shall be made to comply procedures with original Lift Rig Specifi-cations. Fabricator (repairer) has responsibility for detailed repair procedures.

Section 3.2

!. 3.2.1 Use of stress design factors of 3 for See Table 1 (Page 6) for stress minimum yield strength and 5 for evaluation.

E ultimate strength I

_ _ . . _ . . - . _ _ _ . ~ . _ _- _. __ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _

ANSI N14.6-1978 Reactor Vessel (Closure)

Section Referenced Read Lift Rig 3.2.4 Similar stress design factors for See Table 1 (Page 6) for stress load bearing pins , links, and evaluation.

ada pte rs.

3.2.5 Slings used comply with ANSI B30.9. Not applicable since no rope or chain is used for lif ting.

3.2.6 Subject materials to deadweight Vital numbers identified with test or charpy impact test their piece numbers, were im-pact tested using the charpy V-notch method. The required values listed in Section III of ASME Code 1971 Edition through Summer 1973 Addenda, were met at +100F.

Section 3.3 3.3.1 Consideration of problems related No Iffting element is subject to possible galling to lamellar tearing.

3.3.4 Design shall assure even distribu- See Table 1 (Page 6) for tion of the load compliance.

3.3.5 Retainers fitted for load carrying All vital members with connect-components which may become ing pins have cotter pins for inadvertently disengaged positive locking against unplanned disengagement.

3.3.6 Verification that remote actuating Not applicable since no remote mechanisms securely engaged or actuating mechanisms are used, disengaged Section 4.1 4.1.3 Verify selection and use of material Materials verified from mill test reports or certifications and reviewed for compliance to the design specification.

4.1.4 Compliance with f abrication practice - Fabrication practices complied l

in accordance with approved procedures and methods as veri-fled by surveillance and receipt inspection of l c omponents.

l l

l 2

l t

l l

ANSI N14.6-1978 Reactor Vessel (Closure)

Section Referenced Head Lift Rig 4.1.5 Qualification of welders, Weld procedures, materials procedures, and operators and operators were qualified under Section IX of the ASME Boiler and Pressure Vessel Code.

4.1.6 Provisions for a quality All requirements of the assurance program design specification were performed under a quality assurance program in effect at the time of fabrication.

4.1.7 Provisions for identification All material identified by certification of materials piece numbers and/or code numbers in accordance with drawing requirements.

Material certifications conforms to design specification.

4.1.9 Verification that materials Certificate of Equipment or services are produced under letter issued by vendor appropriate controls and verifying compliance with qualifications design specification controls.

Section 5.1 5.1.3 Implementation of a periodic NDE in accordance with ASME testing schedule and a system B&PV Code for Class 2 to indicate the date of Component Supports.

expiration. However, visual inspection of rig prior to use is recommended.

5.1.4 Provisions for establishing Procedures for the use of operating procedures Lift Rig are detailed in the removal of the RV head Instruction Manual.

5.1.5.1 Identification of subassemblies No part is to be exchanged may be exchanged with a part from a similar rig without a detailed study of the geometry and the material pedigree.

5.1.5.2 Suitable Markings Complies 3

ANSI N14.6-1978 Reactor Vessel (Closure)

Section Referenced Head Lift Rig 5.1.6 Maiutaining a full record of history This requirement la being met as follows:

a) This device is used to lift the RV head only, b) The lift rig is qualified for predetermined load, c) The lift rig is visually inspected prior to every lift, d) The lift rig is used during the refueling outage only.

5.1.7 Conditions for removal from service Subject to results of NDE testing and inspection.

Sectior 5.2 5.2.1 Load test to 150 percent and appro- The rig was load tested to priate inspections prior to initial 125 percent of its design use load.

5.2.2 Qualification of replacement parts Replacement parts are to be fabricated to original criteria and will be load tested by Fabric.ator or LP&L.

Section 5.3 5.3.1 Satisfying annual load test or Annual inspection and NDE inspection requirements in accordance with ASME B&PV l

Code for Class 2 Component Supports.

l 5.3.2 Testing following major maintenance there are no requirements for load testing af ter major maintenance. However, it is recommended that any repairs be analytically evaluated and NDE tested on case-by-case basis.

5.3.4 Testing after application of sub- It is recommended that no stantial stresses load test should be done unless the results of the analytical evaluation and NDE testing show a need for it.

4

ANSI N14.6-1978 Reactor Vessel (Closura)

Section Referenced ,

Head Lift Rig 5.3.6 Inspections by operating personnel Not applicable 5.3.7 Nonoperating or maintenance Not applf6able personnel This special lif ting device was designed and fabricated before the issuance of ANSI N14.6-1978 and thus does not meet all requirements in the standard.

However, the f abrication methods met the intent of the standard. The device was load tested prior to first use and will be inspected before every use.

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