ML20128H104
| ML20128H104 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 06/22/1985 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Wilgus W FLORIDA POWER CORP. |
| References | |
| NUDOCS 8507090410 | |
| Download: ML20128H104 (4) | |
Text
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JUN 2 21985 Docket No. 50-302 DISTRIBUTION
-Docket' File; ACRS-10 ORB #4 Rdg RIngram NRC PDR HSilver Mr. Walter S. Wilgus L PDR Gray File Vice President, Nuclear Operations HThompson EBrach Florida Power Corporation OELD H0rnstein ATTN: Manager, Nuclear Licensing EJordan
& Fuel Management BGrimes P. O. Box 14042; M.A.C. H-2 JPartlow St. Petersburg, Florida 33733
Dear Mr. Wilgus:
SUBJECT:
CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT - PUMP AND VALVE INSERVICE TESTING PROGRAM - FIRST 10 YEAR INTERVAL By letter dated June 4,1982, you submitted a revised proposed pump and valve inservice testing program description and requests for relief from selected ASME Code requirements pursuant to 10 CFR 50.55a(g). Although we have not completed our detailed review of your submittal, our preliminary review makes clear to us that your proposed program to implement those ASME Code requirements that you have found to be practical would increase the scope of inservice testing for your facility beyond that currently required by your Technical Specifications. We have concluded that this upgrading of your inservice testing program will further enhance safety.
Based on our preliminary review, we agree with the determination that it is impractical within the limitations of design, geomatry and materials of construction of components, for you to meet certain of the specified ASME Code requirements and that imposition of those requirements would result in hardships or unusual difficulties without a compensating increase in the level of quality or safety. Therefore, pursuant to 10 CFR 50.55a(g)(6)(i),
we hereby grant interim relief until we have completed our detailed review or until September 30, 1985, whichever comes first, from those testing requirements of the ASME Code that you have requested. Moreover, since the scope of the inservice testing will be increased by your proposed program, and the granting of this relief is based only on the impracticality of selected ASME Code requirements, we have determined that the granting of this relief is authorized by law and will not endanger life or property or the common defense and security, and is otherwise in the public interest.
Therefore, you are authorized to, and should proceed to, implement your proposed program (except where your current Technical Specifications are more restrictive).
During the period between now and the date we complete our detailed review of your submittal, you niust comply with both your existing Technical Specifications and your proposed inservice testing program.
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Mr. Wilgus '
In the event conflicting requirements arise for some components, you must comply with the more restrictive requirements (e.g)., shorter testing intervals, increased number of parameters measured.
In other words, the granting of this relief from ASME Code requirements should not be interpreted to give you relief from any of the requiren,ents in your existing Technical Specifications.
When our detailed review of your submittal is complete, we will: (1) issue from our review), and (program (which may contain modifications resulting2) grant final approval of your are determined to be impractical for your facility for the duration of the testing interval.
Sincerely, w............- t J4M J. FaW" John F. Stolz, Chief Operating Reactors Branch #4 Division of Licensing cc:
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Mr. Wilgus In the event conflicting requirements arise for some components, you must comply with the more restrictive requirements (e.g)., shorter inspection intervals, increased number of parameters measured.
In other words, the granting of this relief from ASME Code requirements should not be interpreted to give you relief from any of the requirements in your existing Technical Specifications.
When our detailed review of your submittal is complete, we will: (1) issue final approval of your program (which may contain modifications resulting from our review), and (2) grant relief from any ASME Code requirements that are detennined to be impractical for your facility for the duration of the inspection interval.
Sincerely, John F. Stolz, Chief Operating Reactors Branch #4 Division of Licensing cc:
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Mr. W. S. Wilgus Crystal River Unit No. 3 Nuclear Florida Power Corporation Generating Plant cc:
Mr. R. W. Neiser Bureau of Intergovernmental Relations Senior Vice President 660 Apalachee Parkway and General Counsel Tallahassee, Florida 32304 Florida Power Corporation P. O. Box 14042 Mr. Wilbur Langely, Chairman St Petersburg, Florida 33733 Board of County Commissioners Citrus County Nuclear Plant Manager Inverness, Florida 36250 Florida Power Corporation P. O. Box 219 Crystal River, Florida 32629 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 220, 7910 Woodnont Avenue Bethesda, Maryland 20814 Mr. Tom Stetka, Resident Inspector U.S. Nuclear Regulatory Commission Route #3, Box 171 Crystal River, Florida 32629 Dr. J. Nelson Grace, Regional Administrator U.S. Nuclear Regulatory Commission, Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Mr. Ulray Clark, Administrator Radiological Health Services Department of Health and Rehabilitative Services 1323 Winewood Blvd.
Tallahassee, Florida 32301 Administrator Department of Environmental Regulation Power Plant Siting Section State of Florida 2600 P. lair Stone Road Tallahassee, Florida 32301 Attorney General Departmer.t of Legal Affairs The Capitol Tallahassee, Florida 32304 o