ML17264A907
| ML17264A907 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 06/03/1997 |
| From: | Vissing G NRC (Affiliation Not Assigned) |
| To: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| References | |
| TAC-M98377, NUDOCS 9706050209 | |
| Download: ML17264A907 (6) | |
Text
June 3, f997 Dr. Robert C. Hecre Vice President, Nucleir Operations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING THE R.
E.
GINNA NUCLEAR POWER PLANT THIRD 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN REQUEST FOR RELIEF 17 (TAC NO. H98377)
Dear Dr. Hecredy:
The NRC staff, with assistance from its contractor, Idaho National Engineering and Environmental Laboratory (INEEL), is reviewing and evaluating the third 10-year interval inservice inspection program plan Request for Relief 17 from the American Society of Mechanical Engineers Boiler and Pressure Vessel
- Code,Section XI requirements for R.
E. Ginna Nuclear Power Plant, dated April 9,
- 1997, as supplemented by letter dated May 9, 1997.
Additional information is required in order for the staff to complete its review.
Since we will need your response to accommodate your need for approval
- soon, we request you give this your early attention.
In addition, to expedite the review process, please send a copy of the RAI response to NRC's contractor, INEEL, at the following address:
Michael T. Anderson INEEL Research Center 2151 North Boulevard P.O.
Box 1625 Idaho Falls, Idaho 83415-2209 Sincerely, (Original Signed By)
Docket No. 50-244
Enclosure:
Request for Additional Information Guy S. Vissing, Senior Project Manager Project Directorate I-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation cc w/encl:
See next page DISTRIBUTION:
Docket File PUBLIC PDI-1 R/F S.
Varga OGC G. Bagchi S. Little G. Vissing DOCUMENT NAME:
G: iGINNAiH98377.RAI MEC H(E lIlEÃ~HICIPV ACRS L. Doerflein, Region I T. McLellan y~i To receive a copy of this document, indicate in the box:
"C" = Copy without attachment enclosure "E" = Co with attachment en losure "N" = No co OFFTCE PM:PDi-1 E
LA:PDi-1 D
I-NAME Gvissing/rsi SLittl 1
DATE 06/$
/97 06/
/97
/
/97
<<fic>al Record Copy
'970b050209 970b03 PDR ADOCK 05000244 8,
Qe
- II V
~gP,S REOIj 4, +
O Cy I
0 C
O Ol Cy Yg
/7
~O
++*++
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 3, 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 REGARDING THE R.
E.
GINNA NUCLEAR POWER PLANT THIRD 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN REQUEST FOR RELIEF 17 (TAC NO. H98377)
Dear Dr. Hecredy:
The NRC staff, with assistance from its contractor, Idaho National Engineering and Environmental Laboratory (INEEL), is reviewing and evaluating the third
'0-year interval inservice inspection program plan Request for Relief 17 from the American Society of Mechanical Engineers Boiler and Pressure Vessel
- Code,Section XI requirements for R.
E. Ginna Nuclear Power Plant, dated April 9,
- 1997, as supplemented by letter dated Hay 9, 1997.
Additional information is required in order for the staff to complete its review.
Since we will need your response to accommodate your need for approval
- soon, we request you give this your early attention.
In addition, to expedite the review process, please send 'a copy of the RAI response to NRC's contractor, INEEL, at the following address:
Michael T. Anderson INEEL Research Center 2151 North Boulevard P.O.
Box'-1625 Idaho Falls, Idaho 83415-2209 Sincerely, Docket No. 50-244 Guy S. Viss'in
, 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
Dr. Robert C. Hecredy 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 5 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 Hs. Mary Louise Meisenzahl Administrator, Honroe County Office of Emergency Preparedness ill West Fall Road, Room ll Rochester, NY
-14620 Hr. Paul Eddy New York State Department of Public Service 3 Empire State
- Plaza, Tenth Floor
- Albany, NY 12223
V RR%
E UEST FOR ADDITIONAL INFORMATION
~RL R
T RELIEF RE VEST NO.
17 FOR OCHESTER GAS AND ELECTRIC CORPORATION R.
GINNA NUCLEAR POWER PLANT DOCKET NUMBER 50-244 1.
Sco e Status of Review Throughout the service life of a water-cooled nuclear power facility, 10 CFR 50.55a(g)(4) requires that components (including supports) that are classified as American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Class 1, Class 2,
and Class 3 meet the requirements, except design and access provisions and preservice examination requirements, set forth in the ASME Code Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components,"
to the extent practical within the limitations of design,
- geometry, and materials of construction of the components.
This section of the regulations also requires that inservice examinations of components and system pressure tests conducted during a 120-month inspection interval comply with the requirements in the latest Edition and Addenda of the Code incorporated by reference in 10 CFR 50.55a(b) on the date 12 months prior to the start of the 120-month interval, subject to the limi,tations and modifications listed therein.
The components (including supports) may meet requirements set forth in subsequent editions and addenda of the Code that are incorporated by reference in 10 CFR 50.55a(b) subject to the limitations and modifications listed therein and
'ubject to Nuclear Regulatory Commission (NRC) approval.
The staff has reviewed the available information provided by the licensee in the April 9, 1997, submittal of Relief Request No. 17.
2.
dditional Information Re uired Based on the above review, the staff has concluded that the following information and/or clarification is required to complete the review of the ISI request for relief:
B.
Describe the optimized ultrasonic techniques" referenced in Relief Request No.
17 for the ultrasonic weld examinations of the subject Examination Category B-J welds at the Ginna Nuclear Power Plant.
Is a refracted 'L'ave being used for these examinations?
What percentage of the Code-required coverage does the licensee expect to obtain?
Whereas the examinations have not yet been performed, the staff cannot compare the results at Ginna with the results obtained by other licensees to determine the adequacy of the best effort" examinations.
Encl osut e
J, K