ML20154B395

Provides Addl Info Re Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions

ML20154B395
Person / Time
Site:	FitzPatrick
Issue date:	09/29/1998
From:	Williams J NRC (Affiliation Not Assigned)
To:	James Knubel POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
References
GL-96-06, GL-96-6, TAC-M96812, NUDOCS 9810050195
Download: ML20154B395 (6)

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• Septe m ber 29,1998-Mr. Am:s Knubel Chief Nuclear Officer Power Authority of the State of New York 123 Ms!n Street I White Plains, NY 10601 l

SUBJECT:

JAMES A. FITZPATRICK NUCLEAR POWER PLANT - DRAFT REQUEST FOR l

ADDITIONAL INFORMATION REGARDING GENERIC LETTER 96-06 (TAC NO. M96812) 1

Dear Mr. Knubel:

On July 30,1998, you provided additional information regarding your response to Generic Letter 96-06, "Agurance of Equipment Operability and Containment Integrity During Design Basis Accident Conditions." The NRC staff has determined that additionalinformation regarding your response will be required to complete its review of this issue. A draft copy of the information request is provided in the enclosure. Please review this request and provide your comments and proposed schedule for your response. You may provide this information to me by telephone at (301) 415-1470.

Sincerely, Original Signed by:

Joseph F. Williams, Project Manager Project Directorate 1-1 Division of Reactor Projects - t/11 Office of Nuclear Reactor Regulation Docket No. 50-333 I

Enclosure:

As stated cc w/ encl: See next page DISTRIBUTION:

tDocketfge) S. Little PUBLIC J. Williams PDI-1 R/F OGC J. Zwolinski ACRS S. Bajwa C. Hehl, Region I g;fI DOCUMENT NAME: G:\FITZWl96812A.RAI To receive a copy of this document, Indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy with attachment / enclosure "N" = No copy 'T24-[W' TM7/1[

OFFICE PM:P01 1 [68/ l E LA POI 1 ,, , a l D:PCI-1 ,A l l l NAME JWi t t iams/rsVh" Stittle ///MM SBnJun 4 0U DATE 09/ 25 /98 / ' 09/ /98 Spf 9//%7cd 09/16/98

' Official Record Copy 9810050190 980929 PDR ADOCK 05000333 P PDR

Septe m bsr 29,1998 Mr. J m:s Knub:1 s Chief Nuclear Officer Power Authority of the State of New York 123 Main Street l White Plains, NY 10601 -

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SUBJECT:

JAMES A. FITZPATRICK NUCLEAR POWER PLANT- DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING GENERIC LETTER 96-06 (TAC NO. M96812)

Dear Mr. Knubel:

On July 30,1998, you provided additional information regarding your response to Generic Letter 96-06, " Assurance of Equipment Operability and Containment Integrity During Design Basis Accident Conditions." The NRC staff has determined that additionalinformation regarding your response will be required to complete its review of this issue. A draft copy of the information request is provided in the enclosure. Please review this request and provide your comments and proposed schedule for your response. You may provide this information to me by telephone at (301) 415-1470.

Sincerely, 0riginal Signed by:

Joseph F. Williams, Project Manager Project Directorate I-1 Division of Reactor Projects - l/Il Office of Nuclear Reactor Regulation Docket No. 50-333

Enclosure:

As stated cc w/ encl: See next page DISTRIBUTION:

Docket File S. Little PUBLIC J. Williams PDI 1 R/F OGC J. Zwolinski ACRS S. Bajwa C. Hehl, Region i DOCUMENT NAME: G:\FITZ\M96812A.RAI To receive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy with attachment / enclosure "N" = No copy 12.C.# fM7/f(

OFFICE PM P01 1 /M/lE LA:PDI 1 ojma l D:PCI 1 ,A l l L l NAME JWilliams/rsLI/ " SLittle /Ilf f/ W $8eJws A QU 0 ATE 09/ 4 /98 /* 09/ /98 M9//174Y 09/7(1/98

' Official Record Copy

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James Knubel James A. FitzPatrick Nuclear Power Authority of the State Power Plant of New York cc:

Mr. Gerald C. Goldstein Regional Administrator, Region I Assistant General Counsel U.S. Nuclear Regulatory Commission Power Authority of the State 475 Allendale Road of New York King of Prussia, PA 19406 1633 Broadway New York, NY 10019 Mr. F. William Valentino, President i

New York State Energy, Research, Resident inspector's Office and Development Authority U. S: Nuclear Regulatory Commission Corporate Plaza West P.O. Box 136 286 Washington /$ venue Extension L Lycoming, NY 13093 Albany, NY 12203-6399 Mr. Harry P. Salmon, Jr. Mr. Richard L. Patch, Director Vice President - Engineering Quality Assurance Power Authority of the State Power Authority of the State of New York of New York 123 Main Street 123 Main Street White Plains, NY 10601 White Plains, NY 10601 l Ms. Charlene D. Faison Mr. Gerard Goering Director Nuclear Licensing 28112 Bayview Drive Power Authority of the State Red Wing, MN 55066 of New York 123 Main Street Mr. James Gagliardo White Plains, NY 10601 Safety Review Committee 708 Castlewood Avenue Supervisor Ariington, TX 76012 Town of Scriba Route 8 Box 382 Mr. Arthur Zaremba, Licensing Manager Oswego, NY 13126 James A. FitzPatrick Nuclear Power Plant Mr. Eugene W. Zeltmann P.O. Box 41 President and Chief Operating Lycoming, NY 13093 Officer Power Authority of the State Mr. Paul Eddy i of New York New York State Dept. of l 99 Washington Ave., Suite No. 2005 Public Service Albany, NY 12210 2820 3 Empire S' ate Plaza,10th Floor Albany, NY 12223 Charles Donaldson, Esquire Assistant Attomey Genera! Michael J. Colomb New York Department of Law Site Executi'.e Officer 120 Broadway James A. FitzPatrick Nuclear Power Plant l New York, NY 10271 P.O. Box 41 Lycoming, NY 13093 l

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%,. . . . . ,o Septe m ber 29, 1998 Mr. James Knubel Chief Nuclear Officer  !

Power Authority of the State of l

New York l 123 Main Street l White Plains, NY 10601

SUBJECT:

JAMES A. FITZPATRICK NUCLEAR POWER PLANT- DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING GENERIC LETTER 96-06 l (TAC NO. M96812) I

Dear Mr. Knubel:

On July 30,1998, you provided additional information regarding your response to Generic i

Letter 96-06, " Assurance of Equipment Operability and Containment Integrity Durit:g Design Basis Accident Conditions." The NRC staff has determined that additionalinformatio1 regarding your response will be required to complete its review of this issue. A draft copy of the information request is provided in the enclosure. Please review this request and provid.s your comments and proposed schedule for your response. You may provide this information to me by telephone at (301) 415-1470.

Shcerely,

/ n.*

x Joseph F. Williams, Project Manager Project Directorate I-1 Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation Docket No. 50-333

Enclosure:

As stated cc w/ encl: See next page

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JAMES A. FITZPATRICK NUCLEAR POWER PLANT GENERIC LETTER 96 ASSURANCE OF EQUIPMENT OPERABILITY AND CONTAINMENT INTEGRITY DURING DESIGN BASIS ACCIDENT CONDITIONS DRAFT REQUEST FOR ADDITIONAL INFORMATION

1. In its July 30,1998, submittal, the New York Power Authority (NYPA, also known as the Power Authority of the State of New York) indicated that a total of 23 pipe segment ,

penetrations were potentially susceptible to thermally-induced pressurization. NYPA stated l that 9 of these segments are Reactor Building Closed Loop Cooling (RBCLC) containment l penetrations for which there would be no thermal pressurization damage due to the following two considerations. The first consideration is that fluid pressure would lift the air operated globe valves by pressurizing under the valve seats. The second consideration !s

.that the isolation valves require manual isolation which does not occur until after 10 minutes 1 following a loss-of-coolant accident which would preclude enough heatup within the  !

penetrations to cause thermal pressurization.

Please provide the following information for these penetrations:

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A. Describe the applicable design criteria for the pip ; and valves. Include the required load combinations;

3. Provide a drawing of the valve. Describe the method used to estimate the pressure at which the valve was determined to lift off its seat or leak. Discuss any sources of uncertainty as::ociated with the estimated valve disk lift off or leakage pressure; C. Provide the maximum-calculated stress in the piping run based m the estimated lift off or leakage pressure; D. The licensee states that plant operating procedures only dire she operators to isolate the valves for these penetrations if there are symptoms of a breach in the RBCLC piping and that 10 minutes elapsed time is assumed for operator action. Describe how the plant operating procedures assure that the operators would not tau action at any time prior to 10 minutes; E. Provide the maximum-calculated temperature and pressure for the pipe runs. Describe, in detail, the method used to calculate these pressure and temperature values. This description should include a discussion of the heat transfer model used in the analysis i and the basis for the heat transfer coefficients used in the analysis. Include the lengths I and thicknesses of the piping segments and the type and thickness of the insulation.

2. In its July 30,1998, submittal, NYPA stated that 11 of the 23 pipe segment penetrations were evaluated for the thermal pressure conditions which would occur with the consideration that an isolation valve would lift off its seat to limit the pressure. For these, the licensee evaluated the pipe stresses due to thermal pressurization and other loads in accordance with ASME Appendix F criteria.

Enclosure

2 Please provide the following information for these penetrations:

A. The acceptance criteria includes a load combination for a Normal / Upset Primary Stress condition which is 2.4 times the basic allowable stress at temperature. Since Appendix F does not address Normal / Upset conditions, the staff believes that the 2.4 factor is inappropriate for these conditions. Please provide clarification regarding the appropriate criteria for Normal / Upset thermal pressurization conditions and how it is applied to the l components evaluated; 1

B. The licensee does not combine thermal pressurization loads with occasional hydrodynamic loads. The licensee states that hydrodynamic loads will dissipate before intemal pressure can significantly increase. Describe in detail the hydrodynamic loads which can occur for these penetrations and when they specifically occur relative to thermal pressurization for licensing basis events; C. Describe the applicable design criteria for the isolation valves. Include the required load combinations; D. Provide a drawing of the valves. Describe the method used to estimate the pressure at which the valve was determined to lift off its seat or leak. Discuss any sources of uncertainty associated with the estimated valve disk lift off or leakage pressure; E. In addition, for two of these 11 penetrations (X-18 and X-19), NYPA states that the leak path generated through one of the isolation valves is "non-resealing" due to the seat materials. This infers that the leak would be caused due to significant deformation of the valve intemals. This scenario appears to involve much more uncertainty in determining the peak pressure than for a valve where fluid pressure under a disk acts against a linear-elastic spring resistance. The licensee also relies on the other isolation valve remaining leak-tight until this valve leaks to relieve the fluid pressure. Address the uncertainty in determining the peak pressure and how it is assured that the sole remaining containment isolation valve will remain leak-tight and not undergo similar damage during the pressurization.

3. In its submittal dated July 30,1998, NYPA stated that Pipe Line Numbers 3"-WL-151-1 A and 18 may also be subject to thermal pressurization, but were not analyzed since they are not required for containment integrity. Please verify that containment isolation is the only safety function of this system.

4. In its submittal dated July 30,1998, the licensee also stated that for High Pressure Coolant Injection penetration X-226, isolation valve leakage tests would be required, "perhaps on a periodic basis," to verify sufficient leakage to prevent pressure locking of the valves. Please clarify the specific frequency of the tests necessary to verify the required leakage.

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