ML17264B113
| ML17264B113 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 11/20/1997 |
| From: | Vissing G NRC (Affiliation Not Assigned) |
| To: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| References | |
| TAC-M99702, NUDOCS 9711260168 | |
| Download: ML17264B113 (6) | |
Text
Dr. Robert C. Hecredy ~
Vice President, Nuclea~i perations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649 Novemb
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SUBJECT:
RE(VEST FOR ADDITIONAL INFORMATION REVIEW OF THE RE(VEST 'FOR AMENDMENT DATED SEPTEMBER 29, 1997 CHANGE TO THE TECHINCAL SPECIFICATION RELATED TO THE MAIN STEAN LINE ISOLATION SIGNAL SET POINTS (TAC NO. M99702)
Dear Dr. Hecredy:
We are in the process of reviewing your request for amendment dated September 29,
- 1997, concerning the technical Specification change to the main steam line set points.
In order to complete our review, we have determined the need for additional information.
The enclosed request for additional information provides our concerns for additional information.
Please provide your response within 45 days from receipt of this letter.
,Sincerely, ORIGINAL SIGNED BY. A.
DROMERICK FOR:
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Docket No. 50-244
Enclosure:
Request for Additional Information cc w/encl:
See next page DISTRIBUTION:
Guy S. Vissing, Senior Project Manager Project Directorate I-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation y
F'ocket File PUBLIC PDI-1 R/F B. Boger S.
Bajwa S. Little G. Vissing OGC ACRS C. Hehl, Region I 97<am0~68 97'Zaao PDR ADOCK 05000244 P
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- See Previous Concurrence To receive a copy of this document, indicate in the box:
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&4001 November 20, 1997 Dr. Robert C. Mecredy Vice President, Nuclear Operations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REVIEW OF THE REQUEST FOR AMENDMENT DATED SEPTEMBER 29, 1997 CHANGE TO THE TECHNICAL SPECIFICATION RELATED TO THE MAIN STEAM LINE ISOLATION SIGNAL SET POINTS (TAC NO. M99702)
Dear Dr. Mecredy:
We are in the process of reviewing your request for amendment dated September 29,
- 1997, concerning the Technical Specification change to the main steam line'et points.
In order to complete our review, we have determined the need for additional information.
The enclosed request for additional information provides our concerns for additional information.
Please provide your response within 45 days from receipt of this letter.
Sincerely, Docket No. 50-244 Guy S. Vissing, Senior Project Manager Project Directorate I-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Enclosure:
Request for Additional Information cc w/encl:
See next page
n
Dr. Robert C. Mecredy R.E.
Ginna Nuclear Power Plant CC:
Peter D. Drysdale, Senior Resident Inspector R.E. Ginna Plant U.S. Nuclear Regulatory Commission 1503 Lake Road
- Ontario, NY 14519 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. F. William Valentino, President New York State
- Energy, Research, and Development Authority Corporate Plaza West 286 Washington Avenue Extension
- Albany, NY 12203-6399 Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Nicholas S.
Reynolds Winston 8 Strawn 1400 L St.
N.W.
Washington, DC 20005-3502 Ms. Thelma Wideman
- Director, Wayne County Emergency Management Office Wayne County Emergency Operations Center 7336 Route 31
- Lyons, NY 14489 Ms. Mary Louise Meisenzahl Administrator, Monroe County Office of Emergency Preparedness ill West Fall Road, Room ll Rochester, NY 14620 Mr. Paul Eddy New York State Department of Public Service 3 Empire State
- Plaza, Tenth Floor
- Albany, NY 12223
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.j RE VEST FOR ADDITIONAL INFORMATION RELATED TO CHANGE IN THE MAIN STEAM LINE ISOLATION SIGNAL SET POINTS RE UEST FO MENDMENT DATED S PT MBER 29 1997 GINNA NUCLEAR POWER PLANT DOCKET NO. 50-244 Questions for Ginna's Steam Line Isolation Setpoint Changes (Limiting Condition for Operation (LCO) Table 3.3.2-1, Function 4.d) 1)
Provide the bases for Function 4.d, "High Steam Flow Coincident with Safety Injection and Coincident with T, Low," and Function 4.e, "High High Steam Flow Coincident wit(i Safety Injection" of LCO Table 3.3.2-1.
Provide a discussion of how the bases for these functions will be met with the proposed Allowable Values and Trip Setpoints for Modes.
1, 2and3.
2)
Provide a discussion of the applicable analyses and how these functions are modeled.
Provide the setpoints used in the analyses.
3)
In your submittal you stated,
"...Function 4.e will not provide closure of the MSIVs due to an inadvertent opening of an atmospheric relief or safety valve.
Consequently, only Function 4.d performs this function."
'owever, the setpoint for Function 4.d is higher than the capacity of a single atmospheric relief valve.
Please explain your statement.
4)
You stated, "Choosing lOX RTP equates to 0.66E6 ibm/hr and is also equal to two ARVs opening at 1005 psig."
- However, should both ARVs open, the steam generators would blow down one from each of the ARVs and, therefore, each steam line would only be expected to experience the effect of a single open ARV.
Also, the proposed allowable value would require a steam line break to result in a flow equivalent to the capacity of two ARVs (on a steam line) before the Allowable Value is reached.
Justify your selection of the allowable value for breaks resulting in flows ranging between the proposed value and the sizes assumed in UFSAR Section
- 15. 1.6.
5)
Provide the instrument uncertainty calculation that were performed to confirm that the Allowable Value will not be exceeded.
Discuss the
.analytical value used in this calculation.
Enclosure