ML20044F277
| ML20044F277 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 05/18/1993 |
| From: | Mccabe B Office of Nuclear Reactor Regulation |
| To: | Ralph Beedle POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| References | |
| TAC-M83182, NUDOCS 9305270282 | |
| Download: ML20044F277 (5) | |
Text
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Docket No. 50-333 May 18,1993 Mr. Ralph E. Beedle
-l Executive Vice President, Nuclear Generation Power Authority of the State of New York 4
123 Main Street White Plains, New York 10601
Dear Mr. Beedle:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - POWER UPRATE SUBMITTAL FOR l
THE JAMES A. FITZPATRICK NUCLEAR POWER PLANT (TAC NO. M83182)
By letter (JPN-92-028) dated June 12, 1992, the Power Authority of the State i
of New York (PASNY) submitted an application for an amendment to the James A.
FitzPatri:k Technical Specifications which proposed to increase the authorized maximum power level to 2536 megawatts thermal (Mwt) from the current limit of 2436 Mwt.
Based on our review of the portions of PASNY's submittal related to the structural integrity of pressure-retaining components and their supports, t
reactor internals, core support structures, the control rod drive system, and safety-related equipment, we have identified the need for additional information in order to complete our review. We, therefore, request that PASNY provide a response to the questions enclosed.
In order to facilitate timely resolution of this matter, we request a response within 60 days of receipt of this letter.
This requirement affects one respondent and, therefore, is not subject to Office of Management and Budget review under P.L.96-511.
Sincerely, Original Signed By:
Brian C. McCabe, Senior Project Manager
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Project Directorate I-1 Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation
Enclosure:
Request for Additional Information 6
cc w/ enclosure:
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%%.....+f May 18, 1993 Docket No. 50-333 Mr. Ralph E. Beedle Executive Vice President, Nuclear Generation Power Authority of the State of New York 123 Main Street White Plains, New York 10601
Dear Mr. Beedle:
- 7
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - POWER UPRATE SUBMITTAL FOR..
THE JAMES-A. FITZPATRICK NUCLEAR POWER PLANT (TAC NO. M83182)' '
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By letter (JPN-92-028) dated June 12, 1992, the Power Authority.of the State-i of New York (PASNY) submitted an application for an amendment to the James A..
FitzPatrick Technical Specifications which proposed to increase the authorized maximum power level to 2536 megawatts thermal (Mwt) from the current limit of 2436 Mwt. Based on our review of the portions of PASNY's submittal related to -
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i the structural integrity of pressure-retaining components and their. supports, reactor internals, core support structures, the control rod drive system, and safety-related equipment, we have identified the need for additional information in order to complete our review. We, therefore, request that PASNY provide a response to the questions enclosed.
In order to facilitate timely resolution of this matter, we request a response within 60 days 'of receipt of this letter.
.This requirement affects one respondent and, therefore, is not subject to Office of Management and Budget review under P.L.96-511.
Sincerely,
/dMn L -
C Brian C. McCabe, Senior Project Manager Project Directorate I-l Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
i Request for Additional Information cc w/ enclosure:
See next page i
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Mr. Ralph E. Beedle James A. FitzPatrick Nuclear Power Authority of the State of New York Power Plant cc:
Mr. Gerald C.- Goldstein Ms. Donna Ross Assistant General Counsel.
New York State Energy Office.
Power Authority of the State 2 Empire State Plaza of New York 16th Floor 1633 Broadway Albany, New York 12223 New York, New York 10019 Resident Inspector's Office U. S. Nuclear Regulatory Commission Post Office Box 136 Lycoming, New York 13093 Mr. Harry P. Salmon, Jr.
Resident Manager James A. FitzPatrick Nuclear Power Plant:
Post.0ffice Box 41 Lycoming, New York 13093 Mr. J. A. Gray, Jr.
Director Nuclear Licensing - BWR Power Authority of the State-of New York-123 Main Street White Plains, New York 10601 Supervisor Town of Scriba Route 8, Box 382 Oswego, New York 13126 Mr. John C. Brons, President.
Power Authority of the State of New York 123 Main Street White Plains, New York 10601 Charles Donaldson, Esquire.
Assistant Attorney General New York Department of Law 120~ Broadway:..
New York, New York 110271 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 ' Allendale: Road -
King of Prussia, Pennsylvania.19406
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ENCLOSURE RE00EST FOR ADDITIONAL INFORMATION FITZPATRICK POWER UPRATE REVIEW The Section(s) associated with each of the following items are the applicable Sections of General Electric Report NEDC-32016P, " Power Uprate Safety Analysis for the James A. FitzPatrick Nuclear Power Plant," December 1991 (Proprietary).
1.
(Section 2.5.1) - The evaluation did not address the effect of increased bottom head pressure on the structural and functional integrity of the control rod drive system (CRDS).
Please state the basis for determining the acceptability of the CRDS regarding compliance with the Code. The information provided should include the Code Edition, the Code allowables, the calculated maximum stresses, deformation, and fatigue usage factor for the uprated power conditions, and assumptions used in the calculations.
2.
(Sections 3.3.2 and 3.3.3) - The evaluation of reactor vessel internals only considered the changes in reactor internal pressure.
Please provide a discussion of how the dynamic effects of loss-of-coolant accident, jet reaction, and pipe restraint loads were accounted for in the evaluation of i
the reactor vessel and internals. The discussion should identify the Code i
and Edition used for evaluating stresses and allowables for the reactor vessel and internals.
In addition, please indicate the maximum stresses, fatigue usage factor and location of the highest stressed areas for both the current and uprated power conditions.
3.
(Section 3.5.2) - It appears that the adequacy evaluation tir the reactor coolant pressure boundary piping, pipe supports, and equipment nozzles has not been completed for the power uprate.
Please provide a discussion regarding analysis methods and assumptions used, and compliance with the i
Code of record. The discussion should provide the Code allowables, the calculated maximum stresses, and fatigue usage factors for normal, upset, and faulted conditions.
4.
(Section 3.5.2) - This section stated that some supports may not meet design criteria at uprate and that three nozzles will be qualified with detailed analyses. Please provide more information regarding how these supports and nozzles were qualified for the uprate.
5.
(Sections 3.11.1 and 3.11.2) - Please indicate the Code and Edition used for the power uprate evaluation of balance-of-plant (B0P) piping and pipe supports including anchorages.
It appears that the evaluation was not conclusive for all the B0P pipe supports and equipment nozzles.
Please j
state the methodology, assumptions, and loading combinations used in the B0P piping and pipe support analyses.
In addition, please provide the Code allowables, calculated maximum stresses and fatigue usage factors for i
normal, upset, and faulted conditions.
. 6.
(Section 3.11) - Please provide a discussion on how the current design basis analyses of pipe breaks, jet impingements, and qualification of safety related equipment are affected by the power uprate conditions.
.