ML17263A677
| ML17263A677 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 05/27/1994 |
| From: | Andrea Johnson Office of Nuclear Reactor Regulation |
| To: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| Shared Package | |
| ML17263A678 | List: |
| References | |
| TAC-M80494, NUDOCS 9406070254 | |
| Download: ML17263A677 (5) | |
Text
~p,q A(0m~
ci.
'Cqp 0
Op OO
~O
++*++
Docket No. 50-244 UNITEO STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O.C. 20555-0001 flay 27, 1994 Dr. Robert C. Mecredy Vice President, Nuclear Production Rochester Gas
& Electric Corporation 89 East Avenue Rochester, New York 14649
Dear Dr. Mecredy:
SUBJECT:
GINNA CONTAINMENT STRUCTURAL INTEGRITY TECHNICAL REPORT NO.
500167-7 "RADIAL DISPLACEMENT AND REBAR STRAIN MEASUREMENT FOR EMR 5181,"
HAY 17, 1993 (TAC NO. H80494)
The NRC staff has evaluated the information contained in the subject report (Reference 1).
Enclosed with this letter is our Safety Evaluation (Enclosure
- 1) together with a list of references (Enclosure 2).
In Reference 2 we requested that you reevaluate the potential behavior of the containment base under internal pressure during the containment building integrated leakage rate test (ILRT) performed during the 1993 refueling outage.
The reevaluation was to be based on observations of the behavior of the containment at the base using instrumentation at the bottom of the containment wall.
In response to Reference 2, you proposed to monitor the radial displacement of the containment (Reference
- 3) at the approximate locations monitored during your 1969 preoperational containment structural integrity test.
At our request, you provided your analyses (References 1) on measured data during the 1993 ILRT and other information on the potential behavior of the containment wall at the base.
All other load cases and parametric variations on properties and boundary conditions that were analyzed by you (Table 1 of Reference 4 and Reference
- 5) were found acceptable by the staff (Reference 2).
The staff has carefully reviewed the Reference 1 report regarding radial strain measurements of various rebars of the cylinder portion of the containment at various locations.
Based on these measurements, we conclude that the containment behaves elastically up to the maximum ILRT pressure of 35 psi, which may be extrapolated to the design pressure of 60 psi with some degree of uncertainty.
Uncertainty exists beyond the containment ILRT pressure in that the conditions at the base, as a result of earlier submergence in water, is unknown.
It appears that the best way to assure the structural integrity of the containment is through a well-'planned tendon surveillance program.
OPtQ('4 9406070254 940527 Q PDR ADOCK 05000244 P
PDR~~
~g Hg I;ME~Y (0
'I
Dr. Robert C. Hecredy May 27, 1994 In view of this, we request that you consider establishing a tendon surveillance program, to be carefully implemented to detect broken wires or damaged rock anchors, until your next full ILRT at design pressure.
We request that you continue to obtain strain measurements during the full ILRT to demonstrate the elastic behavior of the containment and to reduce the uncertainties.
This completes our activity on TAC No. H80494.
Sincerely, original signed by Allen R. Johnson, Project Hanager Project Directorate I-3 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Enclosures:
1.
Safety Evaluation 2.
List of References cc w/enclosures:
See next page DISTRIBUTION:
Docket File 50-244 NRC
& Local PDRs PDI-3 Reading SVarga JCalvo WButler SLittle AJohnson OGC ACRS (10)
GBagchi CTan W.
Dean JLinville RI WLazarus RI
- See revious concurrence
."'OF:.FI,CEk);:::::,"':!:'"'".ll"':":
P I-3:L PDI-3: PH
, *ECGB: BC PDI-3: D SLittle A
hnson:dt E~e4
~8 4
OFFICIAL RECORD COPY DOCUHENT NAHE:A:iCONTAIN.HEH GBagchi 05 26 94 WButler
Dr. Robert C. Necredy Hay 27, 1994 In view of this, we request that you consider establishing a tendon surveillance program, to be carefully implemented to detect broken wires or damaged rock anchors, until your next full ILRT at design pressure.
We request that you continue to obtain strain measurements during the full ILRT to demonstrate the elastic behavior of the containment and to reduce the uncertainties.
This completes our activity on TAC No. N80494.
Sincerely,
Enclosures:
1.
Safety Evaluation 2.
List of References All n R. Johns
, Project Hanager Prop t Dire t6rate I-3 Division Reactor Projects - I/II Office of Nuclear Reactor Regulation cc w/enclosures:
See next page
Dr. Robert C. Hecredy R.E. Ginna Nuclear Power Plant CC:
Thomas A. Hoslak, Senior Resident Inspector R.E.
Gi,nna Plant U.S. Nuclear Regulatory Commission 1503 Lake Road
- Ontario, New York '4519 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Ms.
Donna Ross Division of Policy Analysis 5 Planning New York State Energy Office Agency Building 2 Empire State Plaza
- Albany, New York 12223 Charlie Donaldson, Esq.
Assistant Attorney General New York Department of Law 120 Broadway New York, New York 10271 Nicholas S.
Reynolds Winston
& Strawn 1400 L St.
N.W.
Washington, DC 20005-3502 Ms. Thelma Wideman
- Director, Wayne County Emergency Management Office Wayne County Emergency Operations Center 7370 Route 31
- Lyons, New York 14489 Hs. Mary Louise Heisenzahl Administrator, Monroe County Office of Emergency Preparedness 111 West Fall Road, Room 11 Rochester, New York 14620