ML19323C949
| ML19323C949 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 05/14/1980 |
| From: | Richard Bright FLORIDA POWER CORP. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| 3--3-E, 3-0-3-E, NUDOCS 8005190454 | |
| Download: ML19323C949 (3) | |
Text
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3-0-3-e Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 Technical Specification Change Request No. 13, Rev. 1
Dear Sir:
In Technical Specification Change Request No.
13, Rev.
1, dated February 15, 1980, we requested several changes to the Tendon Surveillance Program in accordance with Regulatory Guide 1.35, " Inservice Inspection of Ungrouted Tendons in Prestressed Concrete Containments", Proposed Rev. 3, April 1979.
We are particularly concerned with making the requested change to 4.6.1.6.2 (see attached amended page 3/4 6-9 of our Technical Specifica-tions). This change is justified for the following reasons:
1.
Personnel Safety - We should reduce the time and number of people ex-posed to the Containment Building during Maximum Building Press-ure Testing. The large volume of 50 psig air represents an enor-mous potential energy source.
Therefore, the time the Contain-ment Building is held at 50 psig should be limited to the minimum time required for the Containment Integrated Leakage Rate Test-ing.
2.
Each time the Containment Building is pressurized represents an
' additional stress to the building structures.
This additional stress should also be limited to the minimum time required for the Contain-i ment Integrated Leakage Rate Testing.
3.
Inspection Results - The visual inspection would detect the same de-tectable changes during pressurized or normal pressure condi-tions. Again, the visual inspection would take considerable time and expose more people to a pressurized Containment Building.
General Office 3201 Thirty-fourtn street soutn. P O. Box 14042, st Petersburg. Florda 33733 e 813-866-5151 1
t Office of Nuclear Page Two May 14, 1980 Reactor Regulation Please expedite the evaluation of eliminating the visual inspection of the tendon end anchorages dJring Type A Containment Integrated Leakage Rate Testing.
If you have any questions on this subject, please contact this office.
Sincerely, FLORIDA POWER CORPORATION Ronald M. Bright Acting Manager Nuclear Support Services Enclosure WRKhewM01(D3) 1
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1right states that he is the Acting Manager, Nuclear Support Services Department of Florida Power Corporation; that he is authorized 'on the part of said company to sign and file with the Nuclear Regulatory Comission the information attached hereto; and that all such statements made and matters set forth therein are true and correct to the best of his knowledge, information and belief.
M R. M. /Bri)]ht Subscribed and sworn to before me, a Notary Public in and for the State and County above named, this 14th dqy of May, 1980.
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kw Notary Public Notary Public, State of Florida at Large, i
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CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.
Removing one wire or strand from each of a dome, vertical and hoop tendon chccked for lift off force and determining that over the entire length of the removed wire or strand that:
1.
The tendon wires or strands' are free of corrosion, cracks and damage, 2.
There are no changes in the presence or physical appearance of the sheathing filler grease, and 3.
A minimum tensile strength val.ue of 240,000 psi (guaranteed ultimate strength of the tendon material) for at least three wire or strand sampl'es (one from each end and one at mid-length) cut from each removed wire or strand. Failure of any one of the wire or strand samples to meet the minimum tensile strength test is evidence of abnormal degradation of the containment structure.
4.6.1.6.2 End Anchorages and Adjacent Concrete Surfaces The structural integrity of the end anchorages of all tendons inspected pursuant to Speci-fication 4.6.1.6.1 and the adjacent concrete surfaces shall be demonstrated by determining through inspection that no apparent changes have occurred in the visual appearance of the end anchorage or the concrete crack ratterns adjacent to the end anchorages. Any apparent changes in the visual appearance of the concrete crack patterns is reportable.
4.6.1.6.3 Containment Surfaces The structural integrity of the exposed accessible interior and exterior surfaces of the containment, including the liner plate, shall be determined during the shutdown for each Type A containment leakage rate test (Specification 4.6.1.2) by a visual inspection of these surfaces.
This inspection shall be performed prior to the Type A containment leakage rate test to verify no apparent charges in appearance or other abnormal degradation.
4.6.1.6.4 Containment Dome The containment dome's structural integrity shall be demonstrated at the end of 1 year,18 months, 2 years, 3 years, 40
+10 months (coincident with the first periodic integrated containment leak rate test), and 5 years following the initial containment structural integrity test.
The dome's structural integrity shall be demonstrated by:
CRYSTAL RIVER - UNIT 3 3/4 6-9 Amendment No. 24
,