ML20031F185
| ML20031F185 | |
| Person / Time | |
|---|---|
| Issue date: | 12/09/1977 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | Stello V Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML13319A640 | List:
|
| References | |
| FOIA-81-313 NUDOCS 8110190317 | |
| Download: ML20031F185 (11) | |
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o, UNITED STATES f-NUCLEAR REGULATORY COMMisslON J
WASHINGTON, D. ':. 20555
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V. Stello, Jr., Director, Division of Operating Reactors T
FROM:
D. Eisenhut, Assistant Director for Operational Technology, 00R SUBJe.CT:
STEAM GENERATOR REPLACEMENT AND REPAIR CONTRACT i
Attached is the scope of work prepared by the Engineering Branch for a request for proposal to obtain technical assistance for the review of ste m generator replacement and repair. Although it would be benificial to obtain a contractor in time to assist in the current review of the FPL and VEPC0 steam generator repair programs, we realize that our evaluation of these programs may be completed by the time a contractor can be selected from open bid. However, possible delays in these reviews and the potential f or unanticipated problems
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during the execution of the repair efforts make it desirable to obtain a contractor with the capability to assist in these reviews and evaluations. The selected contractor will then also be available in ti,e event additional steam generator replacement and repair prog ams are proposed and submitted for NRC review.
D. G. Eisenhut, Assistant f irector for Operational Technolor/
Division of Operating Reactors
Enclosure:
As stated
Contact:
R. LaGrange 49-28060 cc:
L. Shao R. Stuart T. Telford B. D. Liaw F. Almeter R. Gamble /
i O. DiIanni R. LaGrange i
J. Guibert R. Cudlin 01gi7310817 h
81-313 PDR
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1 SCOPE OF WORK t
STEAM GENERATOR REPLACEMENT AND REPAIR I.
Introduction Recent problems associated with steam generator tube and tube support degradation at some operating plants have resulted in the potential for the repair or replacement of a steam generator or some of its components.
Any repair or replacement program will involve a large amount of on-s ~te assembly. The objective of this program is to provide the Engineering Branch, Division of Operating Reactor with assistance in reviewing and evaluating licensee's proposed steam senerator repair or replacement programs.
The selected contractor for this work will be required to have experience in steam generator design, field fabrication techniques and prestressed, post-tensioned and reinforced concrete repair techniques. Also, a 7
working knowledge of the ASME Boiler and Pressure Vessel Code and the United States Nuclear Regulatory Commission Regulatory Guides is necessary.
Definition of Tasks i
The selected contractor will be required to complete the tasks described below.
A.
Evaluation of Proposed Steam Generator Modifications The selected contractor will be required to review and evaluate any modifications to existing steam generators propo:
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the intent of the appropriate sections of the ASME Boiler and Pressure Vessel Code or other current structural acceptance criteria. When completed, the review and evaluation will be used as input to the NRC safety evaluation report.
Occasional travel to Washington, D. C. will be required to discuss evaluation results with the NRC staff. Travel to other locations may be necessary to examine the actual steam generator modification,s at the plant site.
B.
Assistance in Evaluating the Feasibility of Unique Repair Metheis -
The selecteo contractor will be required to review and evaluatt N licensee's unicue steam generator repair methods to determine the feasibility of the method. An example of such a method is in-situ retubing of a steam generator.
if required, the contractor will be requested to recomend changes or improvements to the proposed repair method and ensure adequate safety margins. The evaluation will be used by the flRC as input to the safety evaluation report.
Occasional travel to Washington, D. C. and other locations may be necessary to discuss the feasibility evaluation and possible changes to the proposed repair method with the licensee and the x
NRC.
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i C.
Evaluation of Field Fabrication, Cutting and Welding Techniques, Heat Treating Procedures, and NDE Requirements The selected cor;ractor will be required to review and evaluate
. the licensee'<, proposed steam generator repair or replacement program, including field fabrication, cutting ind welding techniques, heat treating procedures, and NDE requirenents to determine if they are in conformance with the applicable sections of the ASME Boiler and Pressure Vessel Code.
If specific Code criteria are not met, the,
contractc/ will be required to determine if the procedures are adequa'te and provide an evaluation to the NRC for use as input to the safety evaluation report.
Occasional travel to Washington, D. C. and other locations may be necessary to discuss with t'ie NRC and the licensee these aspects of his prop,osed repair or replacement program.
D.
Evaluation of Modificatians to the Containment Building or Internal Structures -
The selected contractor will be required to review and evaluate procedures and consequences of removing and subsequently replacing a section of the containment building wall or dome or containment internal walls and structures, if such activities are required to carry out the licensee's proposed steam generator repair or l
replacement program.
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Problems resulting from removal and replacement of a portion of the
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containment building vall or dome will be dependent on the type of containment, i.e., reinforced concrete only or reinforced and
, prestrr. sed. For conventional reinforced concrete only, the contractor will be required to review and evaluate the method used to restore the continuity of the reinforcing bars at the opening. For prestressed con". rete containments, che contractor will be required to review.and evals - ce the licensee's study of the perturbation in the stress / strain distribution created in the structare resulting from removal or cutting of tendons and the subsequent problem of installing new tendons.
For both types of containment the contractor will be required to review and evaluate the proposed methods for eliminating shrinkage of new concrete used to close the opening and welding the liner back in place. These reviews and evaluations will be used as input to the NRC safety evaluation report.
Occasional travel to Washington, D. C. and plant sites where the work is being perfonned may be necessary to discuss containment building or internal structure modifications with the licensee and NRC staff.
E.
Systen' Compatibility Evaltation -
The selected contractor will be required to review and evaluate system compatibility including stress analyses of any additional piping or other components attached to the new or modified steam generators and interfacing with present systems to ensure that they
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meet ASME Boiler and Pressure Vessel Code criteria and/or criteria in the NRC Standard Review Plans. This evaluation will be used as input to the NRC safety evaluation report.
Occasional travel to Washington, D. C. may be necessary to discuss system compatibility with the NRC staff.
F.
Other Technical Assistance on an as Needed Basis -
The selected contractor will be required to provide technical assistance and written input to the NRC staff on all aspects related to the aboved defined tasks. Additionally, the contractor will be required to be available to provide assistance for evaluating unanticipated aspects of steam generator repair or replacement that may ta encountered during the execution of a licensee's program on a' as needed basis consistent with the time frame required for licensing decision. A review and evaluation of such unanticipated incidents would be necessary and the contractor would be required to provide assistance to the NRC staff or actually perfom the review and evaluation for the NRC.
Occasional travel to Washingt:.n, D. C. may be necessary for consultation with the NRC staff and to attend meetings, public hearings and present evaluations to the ACRS.
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III. Reporting Recuirements Letter type reports shall be provided for Tasks A thru E as appifcable to the particular program being reviewed. These reports should include the required review and evaluation and be submitted in a titt frame consistent with NRC licensing requirements.
For work completed on an as needed basis under Task F, brief reports in the form of a technical memorandum will be submitted immediately following completion of the tasks.
IV.
level of Effort It is estimated that 2 manyears of effort will be required during fiscal ye.c 1978.
V.
Publications / References The contractor may find the references identified below to be useful in preparing its submission.
A.
American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Sections III, IX and XI.
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NRC Standard Review Plans VI.
Evaluation Criteria A.
Proposals will be evaluated in accordance with the following weighted factors:
1.
Technical Quality of' Proposal
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- i The methods for achieving the described objectives will be evaluated on the basis of completeness, clarity and feasibility.
4 The proposer's approach will be evaluated on the basis of proolem comprehen'.; ion as demonstrated in the identification of the objectives and the specific commitments made in the proposal which will lead to a successful completion of the project.
2.
Capability and Experience of the Organization Expertise and experience in the design and analysis of steam
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generators typical of those currently installed in operating nuclear power plants.
The contractor will have thorough knowledge of current field fabrication, cutting and welding techniques, heat treating procedures and ASME Code required NDE.
The contractor will have demonstrated the ability to perform
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ASME Code required piping and component stress analysis.
It is not requistd that the contractor have a thorough knowledge of concrete removal and replacement techniques. However, the r-l contractor must have the ability to provide the necessary l
expertise, through a subcontract, within a time frame consistent with NRC licensing requirements.
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3.
Qualification of Project Personnel B4ckground and experience of personnel to be assigned to this contract will be evaluated with respect to education, analytical
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. ability, familiarity with steam generator desig i
knowledge of in-situ repair techniquesns and analyses,
, and knowledge of ASME and other industrial Codes or criteria as appropriat I
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Other Conriderations I.
Cost Evaluation While cost may not be a controlling facto r, it will not be disregarded in the negotiation and award of solicitation.
a contract under this I
2.
B_est-Buy Analysis i
A final best-buy analysis will be perfomed taki the results of the technical evaluation ng into consideration to complete the work within the Governme t', cost analysis, and t
n s required schedule.
Government reserves the right to make an awa d The of the Government, cost and other factors consideto the best r
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Conflict of Interest The two paramount principles that the Comi ssion.nust consider l
in determining whether a conflict of interest 1
j award of this contract are:
would exist by (1) Does the award in any way give rise tn a confli t c that biases or prejudices the results that the Comission expect s from the proposed work.
(2) Would the award put the contractor in an unf i p
a r competitive advantage with respect to other contractors.
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9-E'amples of some of the relationships which would be of concern x
to the NRC are generally describad in AECPR 9-1.54, a copy of which is attached for your information.
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DISTRIBUTION:
Docket File Centrs1 File D. Ross
'EB 2edding T. Novak P. Check Z. Resztoczy E. G. Case V. Benaroys R. !!attson T. Ippolito G. Lainas R. L. fedesco P. Matthews J. C. Glynn D. Fischer R. S. Boyd C. Long R. C. DeYoung V. Stello K. Kniel J. Stolz H. Denton A. Schwencer C. Heltemes G. Lear O. Parr D. Ziemann W. Butler R. Reid D. Vassallo D. Eisenhut R. Denise L. Shao T. Spies R. Baer R. Clark B. Grimes D. Skovholt NRC PDR P. F. Collins Local PDR R. Houston
- 5. Pawlicki 15E (3)
R. Fraley, ACRS(16)
Bethesda Receptionist J. P. Knight M. Kehnemuyi I. Sihweil R. Bosnak J. McGough J. Scinto Meeting Attendees OSD (3)
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