ML20207A675
| ML20207A675 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 05/17/1999 |
| From: | Williams J NRC (Affiliation Not Assigned) |
| To: | James Knubel POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| References | |
| TAC-M83622, NUDOCS 9905270140 | |
| Download: ML20207A675 (6) | |
Text
Mr. James Knubel lily 17,1999
+
Chief NuclearOthcor Power Authority of the Stat 3 of
' New York 123 Main Street White Plains, NY 10601
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT - REQUEST FOR ADDITIONAL INFORMATION REGARDING INDIVIDUAL PLANT EXAMINATION OF EXTERNAL EVENTS (TAC NO. M83622)
Dear Mr. Knubel The NRC staff has determined that additional information regarding the Individual Plant Examination of External Events (IPEEE) for the James A. FitzPatrick Nuclear Power Plant is required to complete its review of this topic. This request is based on our review of your June 26,1996, IPEEE submittal, and your September 17,1998, response to a previous staff l
request for addstional information dated May 26,1998.
In your letter of September 17,1998, you committed to revise the FitzPatrick fire IPEEE to '
reflect resolution of issues associated with the EPRI " Fire PRA Implementation Guide " within
- 120 days of resolution of those issues. Since 3 of the 4 enclosed questions are affected by this EPRI guidance, you are requested to respond to all 4 questions consistent with that commitment This schedule was discussed with Charlene Faison of your staff on May 3,1999.
W you have any questions regarding this matter, please contact me at (301) 415-1470.
Sincerely, Original signed by:
Joseph F. Williams, Project Manager, Section l Project Directorate l Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-333 Q
j
Enclosure:
As stated cc w/ encl: See next page ~
S. Little A. Rubin PUBLIC J. Williams B. Hardin PDl-1 R/F OGC A. Blough, RGN-l S. Black ACRS DOCUMENT NAME: G:\\FITZ\\RAl83622.WPD To receive a copy of this document, Indicate in the box:
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Mr. J mes Knubel May 17,1949 4
Chief NuclearOfficer Power Authonty of the Strts of New York 123 Main Street White Plains, NY 10601 q
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT - REQUEST FOR ADDITIONAL INFORMATION REGARDING INDIVIDUAL PLANT EXAMINATION OF EXTERNAL EVENTS (TAC NO. M83622)
Dear Mr. Knubel:
The NRC staff has determined that additionalinformation regarding the Individual Plant Examination of Extemal Events (IPEEE) for the James A. FitzPatrick Nuclear Power Plant is required to complete its review of this topic. This request is based on our review of your June 26,1996, IPEEE submittal, and your September 17,1998, response to a previous staff request for addstional information dated May 26,1998.
In your letter of September 17,1998, you committed to revise the FitzPatrick fire IPEEE to reflect resolution of issues associated with the EPRI " Fire PRA Implementation Guide " within 120 days of resolution of those issues. Since 3 of the 4 enclosed questions are affected by this EPRI gu6 dance, you are requested to respond to all 4 questions consistent with that commitment. This schedule was discussed with Charlene Faison of your staff on May 3,1999.
If you have any questions regarding this matter, please contact me at (301) 415-1470.
Sincerely, Original signed by:
Joseph F. Williams, Project Manager, Section i Project Directorate l Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-333
Enclosure:
As stated cc w/oncl: See next page DISTRIBUTION:
Docket File S. Little A. Rubin PUBLIC J. Williams B. Hardin PDI-1 R/F OGC-'
A. Blough, RGN-l S. Black ACRS DOCUMENT NAME: G:FITZ\\RAl83622.WPD Ta receive a copy of this document, Indicate in the box:
"C" = Copy without attachment / enclosure "E" = Copy with rttachment/enetosure "W" n 100 copy 0FFICE PDI 1/Pel M /
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DATE 05/ / 7/99 V 05/87/99 05/M /99 05/
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May 17, 1999 Mr. James Knubel Chief NuclearOfficer Power Authority of the State of New York 123 Main Street White Plains, NY 10601
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT - REQUEST FOR ADDITIONAL INFORMATION REGARDING INDIVIDUAL PLANT EXAMINATION
)
OF EXTERNAL EVENTS (TAC NO. M83622) q
Dear Mr. Knubel:
The NRC staff has determined that additionalinformation regarding the Individual Plant Examination of External Events (IPEEE) for the James A. FitzPatrick Nuclear Power Plant is required to complete its review of this topic. This request is based on our review of your June 26,1996, IPEEE submittal, and your September 17,1998, response to a previous staff request for additional information dated May 26,1998.
In your letter of September 17,1998, you committed to revise the FitzPatrick fire IPEEE to reflect resolution of issues associated with the EPRI " Fire PRA Implementation Guide " within 120 days of resolution of those issues. Since 3 of the 4 enclosed questions are affected by this EPRI guidance, you are requested to respond to all 4 questions consistent with that commitment. This schedule was discussed with Charlene Faison of your staff on May 3,1999.
If you have any questions regarding this matter, please contact me at (301) 415-1470.
Sincerely, m
Joseph F. Williams, Project Manager,Section I Project Directorate l Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-333
Enclosure:
As stated cc w/ encl: See next page
s' James A. FitzPatrick Nuclear Power Plant Mr. Gerald C. Goldstein Mr. F. William Valentino, President Assistant General Counsel New York State Energy, Research, Power Authority of the State and Development Authority of New York Corporate Plaza West 1633 Broadway 286 Washington Avenue Extension New York, NY 10019 Albany, NY 12203-6399 Resident inspectors Office Mr. Richard L. Patch, Director U. S. Nuclear Regulatory Commission Quality Assurance P.O. Box 136 Power Authority of the State Lycoming, NY 13093 of New York 123 Main Street Mr. Harry P. Salmon, Jr.
White Plains, NY 10601 i
l Vice President-Engineering Power Authority of the State Mr. Gerard Goenng of New York 28112 Bayview Drive 123 Main Street Red Wing, MN 55066 White Plains, NY 10601 Mr. James Gagliardo Ms. Charlene D. Faison Safety Review Committee Director Nuclear Licensing 708 Castlewood Avenue Power Authority of the State Arlington, TX 76012 of New York 123 Main Street Mr. Arthur Zaremba, Licensing Manager White Plains, NY 10601 James A. FitzPatrick Nuclear Power Plant Supervisor P.O. Box 41 Town of Scnba Lycoming, NY 13093 Route 8, Box 382 Oswego, NY 13126 Mr. Paul Eddy New York State Dept. of Mr. Eugene W. Zeitmann Public Service President and Chief Operating 3 Empire State Plaza,10th Floor Officer Albany, NY 12223 Power Authority of the State of NewYork Michael J. Colomb 99 Washington Ave., Suite No. 2005 Site Executive Officer Albany, NY 12210-2820 James A. FitzPatrick Nuclear Power Plant j
P.O. Box 41 Charles Donaldson, Esquire Lycoming, NY 13093 Assistant Attorney General New York Department of Law Mr. Eric Beckjord 120 Broadway 2909 29* St. NW New York, NY 10271 Washington, DC 20008-3416 Regional Administrator, Region i U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406
4.
REQUEST FOR ADDITIONAL INFORMATION INDIVIDUAL PLANT EXAMINATION OF EXTERNAL EVENTS JAMES A. FITZPATRICK NUCLEAR POWER PLANT
(
j The NRC staff has reviewed information provided on September 17,1998, and has found that j
addetsonal information will be required to conclude that FitzPatrick has met the intent of Generic Letter 88-20, Supplement 4. The information required to complete NRC review is discussed below. Question numbers refer to questions in the portion of the staff's May 26,1998, request
]
for additionalinformation that addressed effects of fires.
- 1. The response to Question #1 relating to the assumed heat loss factors is not sufficient to justify the use of the relatively high heat loss factor used in the assessment.. It is anticipated that the new EPRI guidance will recommend use of a lower heat loss factor in determining the effects of hot gas layers. Thus, hot gas layer damage may become a more significant contnbutor to the fire core damage frequency (CDF). Previous conclusions may need to be reexamined given the new guidance.
We understand that new EPRI guidance is forthcoming and may be helpful in formulating a new response to these questions where revised assumptions may impact the estimated fire CDF. Please review the new EPRI guidance on heat loss factors and formulate a new response to Question #1
- 2. The response to Question #2 relating to delays used in modeling fire propagation does not provide a sufficient basis for the assumed delays (5 minutes and 15 minutes). When making fire damage assessments, a preferable approach to using assumed delay times (that may preclude damage to nearby targets) is to use damage temperatures or radiant heat flux as damage cnteria j
in addition, the response noted characteristics of electrical cabinets which appear to have been credsted with the ability to contain fires intemal to the cabinets. This can be an optimistic assumphon for oil-filled transformers and high-voltage cabinets from which energetic failures may result in damage to nearby targets.
We understand that new EPRI guidance is forthcoming and may be helpful in foimulating a new response to these questions where revised assumptions may impact the estimated fire CDF. Please review the new EPRI guidance on propagation of fires from enclosed ignition sources and formulate a new response to Question #2.
- 3. The response to Question #5 relating to the assumed heat release rates (HRRs) from electncal cabinet fires does not respond adequately to the original Question. The assumed HRRs appear to be too low, and it is not clear whether the assumed properties for the cables are inherent properties or the result of the application of fire retardant. Again, new EPRI guidance is forthcoming and may be helpful in formulating a new response.
Please review the new EPRI guidance on cabinet heat release rates and formulate a new response to Question #5. Please note in the response the assumptions made regarding the properties of the in-cabinet cabling, including the effects of fire retardants.
Enclosure
v-6 4. The response to Question #6 relating to cable qualification is not sufficient. The response addresses combustibility properties and flame propagation tests to confirm the assumed properties. The IEEE 383 standard addresses cable performance in harsh environments, of which flame propagation is but one measure. In particular, a flame propagation test alone does not provide a basis for the assumed 732 *F damage temperature. As an alternative to providing furtherjustification for the 732 *F damage temperature, an assessment of changes in the fire CDF could be made in which a damage temperature of 425 *F is assumed.
Please formulate a new response to Question #6 that includes further justification for the damage temperature assumed, or provide an attemative analysis using a temperature of i
425*F.
I l
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