ML18141A067
| ML18141A067 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 07/26/1983 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Varga S Office of Nuclear Reactor Regulation |
| References | |
| REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR 325, NUDOCS 8308010346 | |
| Download: ML18141A067 (4) | |
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMO:N*n~ VIRGINIA 23261 W. L. STEWART VICE PRESIDENT NUCLEAR OPERATIONS July 26, 1983 Mr. Harold R~ Denton, Director-Office of Nuclear Reactor Regulation Attn:
Mr. Steven A. Varga, Chief Operating Reactors Branch No.
Division of Licensing U. S. Nuclear Regulatory Commission Washington, DC 20555 Gentlemen:
NUREG 0612 - CONTROL OF HEAVY LOADS PHASE I SURRY POWER STATION UNITS 1 AND 2 Serial No. 325 PSE:TLG:jdm:0584C Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 As requested via your letter, dated May 16, 1983, the following is provided for final resolution of the open item, 11 Special Lifting Devices,"
and for demonstrating Surry Power Station Units 1 and 2 conformance to NUREG-0612, "Control of Heavy Loads at Nuclear Power Plants," Phase I.
Special Lifting Devices [Guideline 4, NUREG-0612, Section 5.1.1(4)]
"Special lifting devices should satisfy the guidelines of ANSI Nl4.6-1978, 1Standard for Special Lifting Devices for Shipping Containers Weighing 10,000 Pounds (4500 kg) or More for Nuclear Materials 1 [lOJ.
This standard should apply to all special lifting devices which carry heavy loads in areas as defined above.
For operating plants, certain inspections and load tests may be accepted in lieu of certain material requirements in the standard.
In addition, the stress design factor stated in Section 3.2.1. 1 of ANSI Nl4.6 should be based on the combined maximum static and dynamic loads that could be imparted on the handling device based on characteristics of the crane which will be used.
This is stress design factor on only the weight (static load) of the load and of the intervening components of the special handling device [NUREG-0612, Guideline 5.l.1(4)J.
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VIRGINIA ELECTRIC AND POWER COMPANY TO Mr. Harold R. Denton A detailed comparison was made by Westinghouse of the information contained i.n ANSL.N14.6 with thednformation thatwa,s used to design,
- ,:::*manufacture, insp*ect and test the special lifting devices used at Surry Power 2
- '.Sta ti o~...
T~.e/.compar,i son >shows ::that*:the **speci a lc'rli fting :devices *meet :the
. >intent.of,the<ANSLrequirements.for*.design, fabrication and quality
- :':*_.assur.ance,... *. However ;:;,they :are **not,.tn,,.~strd ct" compliance *with all the ANSI* N 14: 6 *
- .*.requirements for maintenance,:.acce.ptance. testing,* and verification of continuing compliance.
The design, fabrication and quality assurance requirements were defined by Westinghouse on the detailed manufacturing and assembly drawings and purchase order documents.
Manufacturing surveillance with hold points, procedure review and personnel qualification to adequately meet ANSI Nl4.6 requirements were also provided by Westinghouse during the design, fabrication and assembly of the ~pecial lifting devices.
Although ANSI Nl4.6 Section 5.2. 1 required initial load testing at 150 percent maximum load, the reactor vessel head lifting rig had load and lift tests of 100 percent maximum loads performed followed by appropriate non-destructive tests after site assembly, while the reactor internals lifting rig and the reactor coolant pump motor lifting device were not required to be load tested.
However, load tests were performed on these two devices prior to their initial use ln th~ plant.
ANSI Nl4.6 Section 5.3 requires veriflcation of continuing compliance of the special lifting devices by either annual load test at 150 percent of maximum load or non-destructive testing and visual examlnation.
Because these devices are located in the containment these tests are impractlcal to perform.
Maintenance procedures require the reactor vessel head and lnternals lifting rigs to be inspected prior to each refueling and at each containment maintenance period if they are to be used and have been idle for a period of more than six months or the last inspection has been over one year.
The reactor coolant pump motor lifting rig is required to be inspected prlor to each refueling and at each containment maintenance perlod if they are to be used and the last inspection has been over one month.
These inspections are visual inspections of the devices, their critical welds and any bolted joints or connections, and do not require dlsassembly of any components.
These inspections and results are documented per the appropriate procedures and their attachments.
A load cell ls used wlth the reactor vessel head and.
internals lift rigs for continued monitoring during all lifting and lowering.
A stress report has been prepared by Westinghouse to determine the acceptability of the special lifting devices to meet the design requirements of ANSI Nl4.6.
The actual design crlteria used in most cases was that the res~lti ng.. stress.. in. the* load members, when* subjected to the total combined
'1ifting weight, does not exceed one flfth (l/5) of the ultimate strength of the materlal.
These devices when designed and fabricated were not classified
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VIRGINIA. ELECTRIC A.ND POWER COMPANY TO Mr. Harold R. Denton as nuclear safety components thus formal documentation of design requirements
- ,*.-*.,.,,: and -s.tres s. reports were not Te quired/.'* *However, the_ design,.. fabri ca ti on_ and.
quality assurance-requirements were defined on detailed manufacturing drawings
- and 'purchase-order-documents.
,<,Application.:of. the*ANSI Nl4.6 criteria>of,three (3) -and five (5) stress design factors to the special. lifting devices results in acceptable stress limits for tensile and shear stresses with the following exceptions for the reactor internals lifting rig.
(1)
The tensile and shear stresses in the side plates; (2)
The thread shear stress in the leg adaptor; and (3)
The tensile stress at the minimum section of the engaging screw, slightly exceed the criteria that three (3) times the calculated stress must be less than the yield stress.
However, the conservative criteria that five (5) times the calculated stress must be less than the ultimate stress is met, therefore these three items can also be considered acceptable, and in compliance with ANSI N14.6.
In conclusion, the following can be stated:
- l.
The ANSI Nl4.6 requirements for design, fabrication and quality assurance are generally in agreement with those used for the special lift devices.
- 2.
The special lift devices may not be in strict compliance only with the ANSI Nl4.6 requirements for acceptance testing, maintenance and verification of continuing compliance.
However, the load and non-destructive tests performed following fabrication and assembly demonstrates the acceptability of these devices.
Also the present station Maintenance and Administrative Procedures address the concerns of the maintenance and verification of continuing compliance with the ANSI Nl4.6 requirements.
- 3.
The ANSI N14.6 criteria for stress limits associated with certain stress design factors for tensile and shear stresses with design criteria for stress design factors of three (3) and five (5) are adequately satisfied and considered acceptable.
Conformance of special lifting devices used to handle spent fuel shipping cask and/or irradiated specimens to ANSI Nl4.6 - 1978, ANSI B30.8 - 1971 and
- --other-appropriate *criteria-*shall "be verified prior-to:use of-such devices.
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I VIRGINIA ELECTRIC AND POWER COMPANY TO Mr. Harold R. Denton If you have any questions or require further clarification or information
., concerning the-resolutions provided,.pl ease advise.
cc: Mr. James P. 0 1Reilly Regional Administrator Region II Atlanta, Georgia 30303 Mr. Donald J. Burke NRC Resident Inspector Surry Power Station
- ,:o,*Very *truly yours; 4