ML20214N179
| ML20214N179 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 09/04/1986 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Wilgus W FLORIDA POWER CORP. |
| Shared Package | |
| ML20214N180 | List: |
| References | |
| REF-GTECI-A-49, REF-GTECI-RV, TASK-A-49, TASK-OR NUDOCS 8609160142 | |
| Download: ML20214N179 (3) | |
Text
gg_g g September 4, 1986
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Docket No. 50-302 JISTRIBUTION JPartlow
( Jocket M_Le)
RIngram e
NRC PDR~
HSilver L PDR BMozafari Mr. Walter S. Wilgus PBD#6 Rdg RWeller Vice President, Nuclear Operations FMiraglia GEdison Florida Power Corporation 0GC-MNBB-9604 Gray File ATTN: Manager, Nuclear Licensing ACRS-10 NThompson
& Fuel Management EJordan GVissiag P. O. Box 14042; M.A.C. H-3 BGrimes Llois St. Petersburg, Florida 33733 PRandall
Dear Mr. Wilgus:
Subject:
Projected Values of Material Properties For Fracture Toughness Requirements For Protection Against Pressurized Thermal Shock Events 17, 1986 which was submitted in We have reviewed your letter dated January (PTS) Rule,10 CFR 50.61 for the response to the Pressurized Thermal Shock Crystal River Unit No. 3 Nuclear Generating Plant. We have found the material properties of reactor vessel beltline materials, the projected fluence at the inner surface of the reactor vessel at the expiration date of the license, and the calculated RT at the expiration date of the license to be acceptable. The calculated N3 is below the screening criterion of 300 F for circumferential weld mater $dk at the expiration date of the license.
This meets the requirements of the PTS Rule.
The PTS Rule requires that the projected assessment of the RT must be updated whenever changes in core loadings, surveillance measuNMents or other information (including changes in capacity factor) indicate a significant change in the projected values. This ensures that the licensees will track the fluence at the limiting beltline materials throughout the life of the plant to verify their assumptions.
In this regard we request you to submit a reevaluation of the RT and comparison to the predicted value with future Pressure-Temperatures 0bkittalswhicharerequiredby10CFR50,AppendixG.
Our associated Safety Evaluation is enclosed.
Sincerely, I
.d John F. Stolz, Director PWR Project Directorate #6 Division of PWR Licensing-B
Enclosure:
As stated e609160142 860904 PDR ADOCK 05000302 cc w/ enclosure:
P PDR See next page pp gi[
- See previoLs white for concurrences, PBD-6 PBD-6 PBD-6 PBD-6 PBD-6 HSilver;jak*
BMozafari* RWeller* GEdison JStolz 9/3/86 9/3/86 9/3/86 9/ 86 9/ /86
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o Docket No. 50-302 DISTRIBUTION JPartlow Docket File RIngram NRC PDR HSilver L PDR BMozafari Mr. Walter S. Wilgus PBD#6 Rdg RWeller Vice President, Nuclear Operations FMiraglia GEdison Florida Power Corporation 0GC-MNBB-9604 Gray File ATTN: Manager Nuclear Licensing ACRS-10 NThompson
& Fuel Management EJordan GVissing P. O. Box 14042; M.A.C. H-3 BGrimes Llois St. Petersburg, Florida 33733 PRandall
Dear Mr. Wilgus:
Subject:
Projected Values of Material Properties For Fracture Toughness Requirenents For Protection Against Pressurized Thermal Shock Events We have reviewed your letter dated January 17,1986 which was submitted in response to the Pressurized Thermal Shock (PTS) Rule,10 CFR 50.61 for the Crystal River Unit No. 3 Nuclear Generating Plant. We have found the material properties of reactor vessel beltline materials, the projected fluence at the inner surface of the reactor vessel at the expiration date of the license, and the calculated RT at the expiration date of the license
-to be acceptable. ThecalculatedkIS is below the screening criterion of 300*F for circumferential weld mater $dk at the expiration date of the license.
This meets the requirements of the PTS Rule.
must be The PTS Rule requires that the projected assessment of the RT updatedwheneverchangesincoreloadings,surveillancemeasuhNentsorother information (including changes in capacity factor) indicate a significant change in the projected values. This ensures that the licensees will track the fluence at the limiting beltline materials throughout the life of the plant to verify their assumptions.
In this regard we request you to submit a reevaluation of the RT and comparison of the predicted value with future Pressure-Temperaturesbbittalswhicharerequiredby10CFR50,AppendixG.
Our associated Safety Evaluation is enclosed.
Sincerely, John F. Stolz, Director PWR Project Directorate #6 Jivision of PWR Licensing-B
Enclosure:
As stated cc w/ enclosure:
See ne page
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&L,l, (f a W PBD-6 PBD-6 PBD-6 PBD-6 PBD-6 HSilver;jak BMozafari RWeller GEdison JStolz 9/g86 9/J/86 9/ 7 /86 9/ /86 9/ /86
Mr. W. S. Wilgus Crystal River Unit No. 3 Nuclear Florida Power Corporation Generating Plant cc:
Mr. R. W. Neiser State Planning and Development Senior Vice President Clearinghouse and General Counsel Office of Planning and Budget Florida Power Corporation Executive Office of the Governor P. O. Box 14042 The Capitol Building St. Petersburg, Florida 33733 Tallahassee, Florida 32301 Mr. P. McKee Mr. F. Alex Griffin, Chairman Nuclear Plant Manager Board of County Commissioners Florida Power Corporation Citrus County P. O. Box 219 110 North Apopka Avenue Crystal River, Florida 32629 Inverness, Florida 36250 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 220, 7910 Woodmont Avenue Bethesda, Maryland 20814 Resident Inspector U.S. Nuclear Regulatory Commission Route #3, Box 717 Crystal River, Florida 32629 Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Mr. Allan Schubert, Manager Public Health Physiciat Department of Health and Rehabilitative Services 1323 Winewood Blvd.
l Tallahassee, Florida 32301 1
Administrator Department of Environmental Regulation j
Power Plant Siting Section State of Florida 2600 Blair Stone Road Tallahassee, Florida 32301 Attorney General l
Department of Legal Affairs The Capitol Tallahassee, Florida 32304 l
l