L-83-214, Forwards One Time Relief Request Re Tech Spec Requirements for Performing Inservice Insp Following Removal of Reactor Internals.License Amend Fee Not Required
| ML17213B244 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 04/05/1983 |
| From: | Robert E. Uhrig FLORIDA POWER & LIGHT CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| L-83-214, NUDOCS 8304070117 | |
| Download: ML17213B244 (6) | |
Text
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FLORIDAPOWER 8( LIGHTCOMPANY April 5, 1983 L-83-214 Office of Nuclear Reactor Regulation Attention:
Mr. Darrell G. Eisenhut, Director Divi s i on of Licens i ng U.
S. Nuclear Regulatory Commission Washington, D.
C.
20555
Dear Mr. Eisenhut:
Re:
St. Luci e Unit 1
Docket No. 50-335 Inservice Inspection Relief Re uest Please find attached a relief request regarding Technical Specification r equirements for performing Inservice Inspection upon removal of the reactor internals.
In that this represents a one-time relief request, it is our opinion that a license amendment fee is not required.
Very truly yours, Robe E. Uhrig Vice President Advanced System 8 Technology REU/JEM/js Attachment cc:
Mr. James P. O'Reilly, Region II Harold F. Reis, Esquire 8304Q70ii7 830405 PDR ADQCK"'05000855
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Page 1
RELIEF REQUEST gl St. Lucie Unit gl Inservice Inspection A.
Component Identi fication:
Cl ass 1
1.
Examination Category D, Table IWB-2500 1971 Edition through Winter 1972 Addenda 2.
Examination Category B-D, Table IWB-2500 1974 Edition through Summer of 1975 Addenda 3.
Examination Category D, Table IWB-2500 per PSL-1 Tech Spec based upon Item gl requirements (i.e.,
1971 Edition through Winter 1972 Addenda) 4.
Applied only to the Reactor Vessel B.
Examination Requi rement:
1.
Table IW8-2600, Item 1.5 - Volumetric examination of the primary nozz e-to-vesse welds and nozzle-to-vessel inside radi used section.
Extent and Fre uency - All the nozzles of the vessel shall be examined during each inspection interval.
Tne number of nozzles examined during each inspection interval shall be the total number in a vessel divided approximately equally among the expected number of examinations during the inspection interval.
The resulting number shall include a representative sampling among each group of nozzles of ccmparable size.
2.
Table IWB-2600,'tem 81.4 - The examination of each nozzle sha cover 10(5 o
the volume per FIG.
IWB-2500 D.
All nozzles shall be examined during each ins ection interval.
3.
PSL-1 Tech Spec Surveillance re uirements - 4.4.10.1, Table 4.4.6, 3/4 4 Volumetric examination of primary nozzle-to-vessel welds and nozzle-to-vessel inside radiused section.
Extent and fre uency - The required examinations will De performed by mechanized techniques whenever the internals are removed; one (1) outlet and one (1) inlet nozzle during the first two-thirds of the inspection interval (not to exceed two 2
each C.
Identification of Impractical Code Re uirement:
Performance of the nozzl e-to-vessel wel ds and nozzle-to-vessel inner radiused section (inlet and outlet) mechanized examinations during the second inspection eriod upon removal of the reactor internals per ech pec requl rements.
Page 2
St. Lucie Unit gl Inservice Inspection D.
Basis for Relief:
1.
To date, FPL has not been issued a safety evaluation report on the updated ISI program (i.e.,
1974 Edition through Summer 1975 Addenda),
submitted to the NRC on July 1, 1977 (ref. L 203).
However, the NRC issued an interim letter of approval on December 20, 1977 signed by J.
K. Davis, Acting Chief, Operations Reactor Branch g2, which requires FPL to use the most restrictive of either the Tech Spec or the updated ISI program.
2.
During the first ins ction period, FPL performed mecnanized examinations o
both out et nozz e-to-vessel welds and nozzle-to-vessel inside radi used sections.
These examinations were conducted from the inside bore of the nozzles mployi ng the straight beam ultrasonic method.
The later codes permit deferral of nozzle inspections to the end of the inspection i nterval pr ovi ded:
At least 25$ of the nozzles are examined by the end of the first inspection period; and that examinations are conducted fran the inside bore -of the nozzles employing the straight beam ultrasonic method.
3.
Performing the examinations during the second inspection period would result in hardship; i.e., economical, expenditure of
- manpower, and exposure of personnel frcm approximately 16.5 to 50 man-rem without a compensatory increase in level of quality a nd sa fety.
E.
Alternative Examinations:
1.
Perform a visual examination of the vessel interior surfaces that could be subject to physical damage as a result of removing the core barrel.
Further, perform visual examination of nozzle(s) weld and adjacent surfaces.
2.
Perform the mechanized volumetric examinations of the primary nozzle-to-vessel welds and nozzle-to-vessel inside radiused section at or near the end of the first inspection interval.
F.
Implementing Schedule:
At or near the end of the first inspection interval.
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