ML20136B061
| ML20136B061 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 11/08/1985 |
| From: | Harold Denton Office of Nuclear Reactor Regulation |
| To: | Andrews R OMAHA PUBLIC POWER DISTRICT |
| References | |
| NUDOCS 8511200122 | |
| Download: ML20136B061 (5) | |
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November 8, 1985 Docket'No. 50-285
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Mr. R. L. Andrews Division Manager - Nuclear Production Omaha Public Power District
- 1623 Harney Street Omaha, Nebraska 68102
Dear Mr. Andrews:
SUBJECT:
INSERVICE INSPECTION AND TESTING PROGRAM - RELIEF FROM ASME BOILER AND PRESSURE VESSEL CODE, SECTION XI By letter dated July _7,1983, you requested relief from the ASME Boiler and
. Pressure Vessel Code,Section XI for the second 10-year interval at the Fort Calhoun Station, Unit No. 1.
You determined that the Code required inspection and testing of certain components to be impractical. By letter dated September 26, 1983, you forwarded your Inservice Inspection and Testing (ISI)
Program for the second 10-year interval at the Fort Calhoun Station, Unit No.1.
Your program reflected the reliefs that were requested. By letters dated November 15, 1983, January 10, 1984, and March 19, 1984, you provided updated information regarding your relief requests and program.
In order to have one document that reflects the complete program and relief requests, you submitted on February 13, 1985 an update.
By letter dated September 30, 1983, we granted relief, on an interim basis until September 26, 1984, from those inservice testing requirements of the Code for the pumps and valves that you requested. We included our Safety Evaluation to support our determination.
In the same letter, we stated that our review of your relief requests for Class 1, 2, and 3 examinations was continuing and our approval of your relief requests was not necessary at that time. By letter dated April 6,1984, we granted relief from the Class 1, 2, and 3 examinations that you requested. We included a Safety Evaluation to support our determination.
In addition, by letter dated October 9,1984, we granted a further relief, on an interim basis until September 26, 1985, from the inservice testing requirements of the Code for the pumps and valves that you requested.
Our review of your relief requests associated with the pumps and valves is not yet complete, and the basis for granting _the current interim relief as
' discussed in our September 30, 1983 Safety Evaluation has not changed. We still agree on an interim basis with you that certain code testing requirements are impractical. We also believe that our interim approval will not endanger life or property or the common defense and security and is otherwise in the public interest.
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,. Therefore, pursuant to 10 CFR 50.55a(g)(6)(1), we hereby grant relief, on an interim basis pending completion of our detailed review, from those inservice testing requirements of the ASME Code that you requested. Therefore, you are authorized to continue your program for the second 10-year interval at the Fort Calhoun Station, Unit No. 1.
During the period between now and the date we complete our detailed review of your relief requests, you must comply with both your ISI program and your technical specifications.
In the event conflicting requirements arise for some components, you must comply with the more restrictive requirements.
In other words, the granting of relief from the Code requirements should not be interpreted to give you relief from any of the requirements in your existing Technical Specifications.
Sincerely, Original sigucd by Darrell G. Eisenhut n[ Darrell G. Eisenhut, Acting Director
/ Office of Nuclear Reactor Regulation cc: See next page DISTRIBUTION:
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. l Therefore, pursuant to 10 CFR 50.55a(g)(6)(1), we hereby grant relief, on an interim basis pending completion of our detailed review, from those inservice testing requirements of the ASME Code that you requested. Therefore, you are authorized to continue your program for the second 10-year interval at the Fort Calhoun Station, Unit No. 1.
During the period between now and the date we complete our detailed review of your relief requests, you must comply with both your ISI program and your technical specifications.
In the event conflicting requirements arise for some components, you must comply with the more restrictive requirements.
In other words, the granting of relief from the Code requirements should not be interpreted to give you relief from any of the requirements in your existing Technical Specifications.
Sincerely, t
Harold R. Denton, Director Office of Nuclear Reactor Regulation cc: See next page DISTRIBUTION:
Docket File NRC PDR RDiggs L PDR OPA, CMiles ORB #3 Rdg ACRS-10 HThompson MVirgilio PMKreutzer-3 ETourigny TBarnhart-4 OELD BGrimes SECY EJordan Gray File +4
- See previous white for concurrences
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o 'Therefore, pursuant to 10 CFR 50.55a(g)(6)(1), we hereby grant relief, on an
' interim basis pending completion of our detailed review, from those inservice testing requirements of the ASME Code that you requested. $h have determined that the relief granted neither increases the probability or consequences of accidents previously considered nor decreases safety margins and tjat, therefore, it does not involve a significant hazards consideration] ouT PE/ CD Therefore, you are authorized to continue your program for the second 10-year interval at the Fort Calhoun Station, Unit No. 1.
During the period between now and the date we complete our detailed review of your relief requests, you must comply with both your ISI program and your technical specifications.
In the event conflicting requirements arise for some components, you must comply with the more restrictive requirements.
In other words, the granting of relief from the Code requirements should not be interpreted to give you relief from any of the requirements in your existing Technical Specifications.
Sincerely, llarold R. Denton, Director Office of Nuclear Reactor Regulation cc: See next page DISTRIBUTION:
Docket File NRC PDR RDiggs L PDR OPA, CMiles ORB #3 Rdg ACRS-10 HThompson MVirgilio PMKreutzer-3 ETourigny TBarnhart-4 OELD l
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Mr. R. L. Anorews Fort Calhoun Station Omaha Public Power District Unit No. I cc:
Harry H. Voigt, Esq.
LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, NW Washington, D.C.
20036 Mr. Jack Jensen, Chairman Washington County Board of Supervisors Blair, Nebraska 68023 Metropolitan Planning Agency ATTN: Dagnia Prieditis 7000 West Center Road Omaha, Nebraska 68107 Resident. Inspector U.S. Nuclear Regulatory Commission P. O. Box 309 Fort Calhoun, Nebraska 68023 Mr. Charles B. Brinknen, Manager Washington Nuclear Operatins C-E Power Systems 7910 Woodmont Avenue Bethesda, Maryland 20814 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Office of Executive Director for Operations 611 Ryan Plaza Drive, Suite 1000 Arlingto'n, Texas 76011 I
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