L-83-254, Requests Relief from Tech Spec 4.4.10.1.a & 10CFR50.55a(g) Requirements Re Inservice Insp.Relief Requested Due to Problems W/Thermal Shield Which Necessitated Removal of Reactor Internals
| ML17213B310 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 04/22/1983 |
| From: | Robert E. Uhrig FLORIDA POWER & LIGHT CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| L-83-254, NUDOCS 8304280252 | |
| Download: ML17213B310 (6) | |
Text
REGULAY INFORMATION DISTRIBUTI(+SYSTEM (RIBS>
ACCESSION NBR:8304280252 DOC ~ DATE! 83/04/22'OTARIZED:
NO FAOIL:50-335 St. Lucie Plantg Uni;t 1E Florida Power 8 Light Cos
'AUTH NAME AUTHOR AFFILIATION UHRIGE R ~ F ~
Florida Power L Light Co, REC IP ~ NAME RECIPIENT AFFILIATION EISENHUTED>G.
Division of Licensing
SUBJECT:
Requests r el ief from Tech 'Spec 4.4..10si
~ a 8
10CFR500'55a(g) requir ements r e inservice insp,Relief r equested due to problems w/thermal shield which necessi,tated removal of reactor intenals.
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P. O. BOX 14000, JUNO BEACH, FL 33408 FLORIDAPOWER 5 LIGHT COMPANY Apri 1 22, 1983 L-83-254 Office of Nuclear Reactor Regulation Attention:
Mr ~ Darrel 1 G ~
Ei senhut, Director Division of Licensing U.
S.
Nuclear Regulatory Ccmmi ssi on
)la shington, D.
C.
20555
Dear Mr. Ei senhut:
Re:
St. Luci e Un it I Docket Ho. 50-335 Relief Request frcm Technical Specification Inse rvice Inspection Re ui rements Technical Specification 4 ~ 4. 10. I.a and 10 CFR 50.55 a (g) contains certain IS I schedular requirements as well as a specific ASME Code Edition ~
Please find attached a relief request from certain of these requi rements
~
Tni s reli ef is required during the current extended outage caused by pr obl ems wi th the thermal shield which necessitated removal of the reactor internals
~
These requests have previ ously been di scussed wi th your staff.
Very truly yours, Rob
~ Uhrig Vice President Advanced System 5 Technology REU/J EM/js Attachment cc:
Mr ~ James P
~ O'Reil ly, 'Regi on II Harold F.
Rei s, Esquire ool saoemoa52 SSOeia 8
PFOPLE... $ERVING PEOPLE
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Page 1
St. Luci e Unit gl Inservice Inspection RELIEF REQUEST ala A.
Component Identification: Class 1
1.
Reactor Pressure
- Vessel, Excluding Closure Head a.
Al 1 pressure
- retaining welds b.
'Al 1 i ns i de radi used sect i ons c.
Interior clad surfaces d.
Interior sur faces and internal support attachments to vessel wall e.
~ Removable core - support structures B.
Examination Requi rement:
1.
Extent and frequency:
The required examinations as applicable will be performed at or near the end of the 10-year Inspection Interval or when the internals are removed for other reasons certain examinations are subject to examination.
Basis:
St.
Luci e Unit 1 Tech Spec (i.e.,
1971 Edition thru Minter 1972 Addenda and 10 CFR 50.55 a(g)
(1974 Edition thru Summer
. 1975 Addenda)
C.
Identification of Relief frcm Code Requirement:
2 ~
FPL opts to conduct mechanized examinations of the reactor vessel during the second inspection period for credit in lieu of the end of the inspection interval (i.e., third snspection period).
FPL opts to conduct the following vessel examinations to the A3'hE 1977 Code Edition thru Summer 1978 Addenda, and R.G. 1.150, Revision 1,
except for the following examinations, which were conducted during the first inspection period to the Tech Specs and the ASHE 1974 Edition thru Summer 1975, which also meet the 1977 thru Summer 1978 requirements.
These examinations include two (2) outlet nozzle-to-vessel welds and nozzle-to-vessel inside radiused
- sections, and were conducted from the inside bore of the nozzles.
a.
Examination Category B-A, First Inspection Interval.
The examinations shall include essentially 10(5 of the length of each circumferential and longitudinal weld in the vessel shell (which includes two (2) core belt region welds), shell-to-flange weld, and the accessible length of each circumferential and meridional weld in the vessel head.
b.
Examination category B-D, Inspection Program 8, First Inspection Interval.
The examinations shall include 10(@ of each nozzle-to-vessel weld and adjacent areas (radiused sections).
r 41 Page 2
c.
Examination Category B-N-1.
The exami nation of the interior of the vessel.
d.
Examination Category B-N-3.
The exami nation of the removable core support structures.
e.
Examination Category B-J.
Pressure retaining weld in piping.
0.
Basis for. Relief:
1.
The proximity to the end or near the end of the first inspection interval; i.e.,
FPL is currently in an extended outage and is nearing the end of the second inspection period (effective August 1983).
13uring this outage, it was found necessary to remove the internals because of problems related to the reactor vessel thermal shield.
2.
In order to maximize the benefits of inservice inspection of the vessel due to the problems associated with the thermal shield and its removal, and to provide information to address Pressurized Tnermal Shock.
The results of these'data wil 1 be used to define specific flaw distrioution by modifying the current conservative generic flaw distribution (OCTAYIA) assumed in licensing calculations in the absence of inservice inspection data.
3.
Performing the examinations during the end of the second inspection period would minimize the hardships; i.e., economically and by the reduction of radiation exposui e to personnel (cur rent examinations range from 16.5 to 50 man-rem).
As a consequence, there would be a
compensatory increase'in the level of quality and safety.
4.
Performing the examinations to the ASME 1977 Code Edition thru Summer 1978 Addenda is consistent with the examinations conducted on St.
Luci e Unit No.
2 and complies with the regulations of 10 CFR 50.55 a(g)4.
E.
Alternative Examinations:
1.
Perform a manual volumetric and surface exami nation of two (2) inlet nozzle-to-extension welds and extension-to-elbow welds (Category 8-J).
Note:
These welds are not classified as safe end welds by code definition.
F.
Implementation Schedule:
1.
Perform mechanized examination of the reactor vessel during the second inspection period for credit in lieu of the end of the Inspection Interval (i.e., third inspection period).