ML17264B005
| ML17264B005 | |
| Person / Time | |
|---|---|
| Site: | Ginna |
| Issue date: | 08/25/1997 |
| From: | Vissing G NRC (Affiliation Not Assigned) |
| To: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| References | |
| TAC-M95759, NUDOCS 9708290197 | |
| Download: ML17264B005 (7) | |
Text
9 Dr. Robert C. Hecredy ~
Vice President,
- Nuclea, perations Rochester Gas and Electric Corporation 89 East Avenue Rochester; NY 14649 Aest 25, 1997
SUBJECT:
RE(VEST FOR ADDITIONAL INFORMATION SPENT FUEL POOL MODIFICATIONS (TAC NO. H95759)
Dear Dr. Hecredy:
We are in the process of reviewing your March 31, 1997, application for an amendment to the Technical Specifications relating to the proposed spent fuel pool modifications.
In order to continue our review, we have determined the need for additional information in the area of chemical analysis.
The enclosed request for additional information provides our concerns and since we are approaching the date when you requested the amendment, please provide your response as soon as possible.
Sincerely, ORIGINAL SIGNED BY:
Docket No. 50-244 Guy S. Vissing, Senior Project Manager Project Directorate I-l Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
Request for Additional Information cc w/encl:
See next page DISTRIBUTION:
PUBLIC PDI-1 R/F B. Boger A. Dromerick S. Little G. Vissing OGC ACRS L. Doerflein, RI K. Parczewski DOCUMENT NAME:
G: iGINNAiH95759.RAI Nlg IFIII.P gLPHPLUPgmPIII To receive a copy of this document, indicate in the box:
"C" = Copy without attachment enclosure "E" = Co ith attachment enclosure "N".- No co OFFICE PM:PDI-1 E
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 25, 1997 Dr. Robert C. Hecredy Vice President, Nuclear Operations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - SPENT FUEL POOL MODIFICATIONS (TAC NO. H95759)
Dear Dr. Hecredy:
We are in the process of reviewing your March 31, 1997, application for an amendment to the Technical Specifications relating to the proposed spent fuel pool modifications.
In order to continue our review, we have determined the need for additional information in the area of chemical analysis.
The enclosed request for additional information provides our concerns and since we are approaching the date when you requested the amendment, please provide your response as soon as possible.
Sincerely, Docket No. 50-244 Guy
. Vissing, Se 'or Project Manager Project Directorate I-l Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
Request for Additional Information cc w/encl:
See next page
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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 Hr. F. William Valentino, President New York State
- Energy, Research, and Development Authority Corporate Plaza West 286 Washington Avenue Extension
- Albany, NY 12203-6399 Charlie Donaldson, Esq.
Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Nicholas S.
Reynolds Winston
& Strawn 1400 L St.
N.W.
Washington, DC 20005-3502 Hs. Thelma Wideman
- Director, Wayne County Emergency Management Office Wayne County Emergency Operations Center 7336 Route 31
- Lyons, NY 14489 Ms. Mary Louise Heisenzahl Administrator, Monroe County Office of Emergency Preparedness 111.West Fall Road, Room 11 Rochester, NY 14620 Hr. Paul Eddy New York State Department of Public Service 3 Empire State
- Plaza, Tenth Floor
- Albany, NY 12223
RE VEST FOR ADDITIONAL 'INFORMATIO RELATING TO THE PROPOSED SPENT UEL POOL MODIFICATIONS R.E.
GINNA NUCLEAR POWER PLANT In the submittal you have indicated that some spent fuel racks with
- Boraflex, used presently in the spent fuel pool (SFP), will be retained.
~ Although the analysis described in the submittal was based on a very conservative estimation of the degree of Boraflex degradation during its exposure in the
- SFP, experience has shown that this degradation depends on several factors which may be difficult to estimate.
For example, maintaining low silica 'level in the SFP water may accelerate degradation of the polymer with consequential higher loss on. boron carbide.
Therefore, many plants instituted surveillance programs consisting of inspection of coupons and/or measurement of silica concentration in the SFP water.
Are you intending to have a Boraflex surveillance program in the reracked SFP?
If so, describe the program.
If not, provide your basis.
In the new fuel racks, borated stainless steel panels will remain in contact with the components made from a regular stainless steel.
Because of the slightly different chemical composition of these materials, galvanic cells may form in a boric acid solution and this may be a source of corrosion.
Show that this phenomenon will not contribute to a significant degradation of poison material.
Describe the inspection program of borated stainless steel panels before their incorporation into the spent fuel racks.
Although tests with borated stainless steel have indicated that in the SFP environment no measurable corrosion degradation takes place, the importance of its role in reactivity control in the SFP,, makes it advisable to have a surveillance program which would provide additional assurance that at all times there will be enough poison material in the SFP.
Are you planning to institute such a program in your plant?
If so, describe the program.
If not, provide your basis.
With a larger number of fuel assemblies stored in the SFP it is expected that more corrosion products and other impurities will be generated in the SFP.
Is the presently existing purification system adequate to handle this increased amount of impurities?
Provide your basis.
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