ML19319D472
| ML19319D472 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 11/05/1976 |
| From: | Rodgers J FLORIDA POWER CORP. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8003170599 | |
| Download: ML19319D472 (5) | |
Text
% -nu 195 u.s. NUCLE AR CEGULATOT1Y C^MMISSION DOCKET NUMIE R cAn.
30-30 2 NRC DISTRIBUTION FOR PART 50 DOCKET M ATERIAL TO:
Mr Stolz FROM:
Fla Pwr Corp DATE OF DOCUMENT 11-5-7h St Petersbo g, Fla J T ROdgers oATE RECElvEO OLE TTE R UNOTORIZED PROP IMUTFORM NUMBER OF COPIES RECE4VE D D ORIG 8N AL hUNC L ASSIFI E D M' COP Y 1CC DESCRIPT60N ENCLOSURE Ltr trans the fOllOwing:
Info COnCerning integrated Irradiation Program fOr Reactor Vessel. Surveillance Specimens.....
PLANT NAME:
Crystal River #3
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November 5,1976 s
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s (M4 Mr. John Stolz e'-
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Subject:
Crystal River Unit 3, Docket No. 50-302, Integrated Irradiation Program for Reactor Vessel Surveillance Specimens
Dear Mr. Stolz:
Florida Power Corporation letter dated September 28,1976, re-garding the surveillance program for reactor vessel surveillance specimens for Crystal River Unit 3 (CR-3), indicated that installation of surveillance cap-sules in CR-3 would be deferred until the first refueling. We have reviewed this matter further, and concluded that we will install two surveillance. cap-sules at this time, for irradiation during the first fuel cycle. Additional cap-sules will, of course, be installed at the first refueling as previously discussed with you.
We consider the above approach to meet the requirements of Appendix H of 10CFR50 The planned capsule installation and removal sched-ule meeting Appendix H requirements is shown on Table 1.
A capsule installed at initial fuel load will be removed at the first refueling and tested as re' quired by the Appendix H, Paragraph II. C. 3. c withdrawal schedule which requires a capsule to be removed at hat time.
The capsules loaded at the initial fuel load will be those contain-ing fracture mechanics type specimens of weld materials, as well as normal tensile and Charpy specimens (see Table 2, attached). These capsules are the capsules which NRC has previously approved for use in CR-3.
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General Office 3201 Thirty-fourtn street soutn. P.O. Box 14042, st. Petersburg, Florida 33/33 813-866-5151 o
Page 2 As indicated above, we consider the above described surveillance capsule irradiation schedule to meet 10CFR50, Appendix H, requirements. If you have any comments on it, we would appreciate receiving them as soon as pos sible.
2-Very truly yours, 1
J. T. Rodgers Asst. Vice President 4
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TABLE 1 REACTOR VESSEL MATERIAL IRRADIATION SCHEDULE Specimen Ins tallation Removal 1.
Capsule A End of First Cycle Standby 2
Capsule C End of First Cycle End of lith Cycle 3.
Capsule E End of First Cycle End of 7th Cycle 4.
Capsule B Initial Fuel Load End of 1st Cycle 5.
Capsule D Initial Fuel Load End of 6th Cycle 6
Capsule F End of First Cycle End of 3rd Cycle Note:
Capsules B, D and F contain compact tension specimens as well as Charpy and tensile specimens.
TABLE 2
_ _.._ @NTENTS OF EACH OF TWO CAPSULES TO BE INSTALLED AT INITIAL FUEL LO ADING Number of Specimens Material Description Tensile Charpy 1/2 TCT 1.
Weld Metal, WF-209 2
12 8
2 Weld-HAZ 0
12 0
Heat C4344-1-transverse 3.
Base Material 2
12 0
Heat C4344-2-transverse Total per Capsule 4
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