ML18110A744
| ML18110A744 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 02/19/1976 |
| From: | Robert E. Uhrig Florida Power & Light Co |
| To: | Jennifer Davis NRC/IE |
| References | |
| L-76-61 | |
| Download: ML18110A744 (17) | |
Text
BOX 013100 MIAMI FLORIDA I
1 FLORIDA POWER 8( LIGHT COMPANY Eebruary 19, 1976 L-76-61 Mr. John G. Davis, Acting Director Office of Xnspection and Enforcement U.
S. Nuclear Regulatory Commission Rashington, D.
C.
20555
Dear Mr. Davis:
Re:
10 CER 50.55(e)
Final Report Xmproper Containment Boundary Quality Group Designation St. Lucie Unit No.
1 On January 22, 1976, I forwarded an interim report to you concerning the improper quality group designation of a number of: the containmen boundary penetrations at St. Lucie Unit No. l.
A final report of this incident is herewith forwarded to you in accordance with 10 CFR 50.55(e).
Yours very truly, Robert E. Uhrig Vice President:
REU:nch Attachment cc:
N.
S. kidd Norman C. Moseley Jack R.
- Newman, Esq.
HELPING BUILD FLORIDA
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FLORIDA POWER 6 LIGHT COMPANY ST.
LUCIE PLANT UNIT gl FINAL REPORT CONTAINMENT BOUNDARD QUALITY GROUP DESIGNATION
- February, 1976
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SUMMARY
During an updating of piping and instrumentation
- diagrams, it was noted that the lines and containment isolation valves attaching to fourteen containment penetration assemblies were designated as Quality Group C.
Since these lines and their respective isolation valves comprise part of the containment
- boundary, the appropriate quality group designation is "B" as stated in FSAR Table 3.2-1.
A review to determine the additional NDE and other QA and code r'equirements necessary to upgrade Quality Group C lines and,valves to Quality Group B has been performed.
The up-grading efforts are complete with no major repair work having resulted from i.he efforLs.
II.
DESCRIPTION OF DEFICIENCY The following containment penetration isolation bounda'ry piping had been procured as Quality Group C in total or in part up to and including the containment isolation valves located outside containment:
PENET.
NO.
SERVICE 14 Nitrogen Supply 1S g 17 g 19 g 21 Containment Fan Coolers Cooling Water Return 16,18,20,22 Containment Fan Coolers Cooling Water Supply 23 Reactor Coolant Pump Cooling Water Supply 24 Reactor Coolant Pump Cooling Water Return
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PENET.
NO.
I r'RVICE 31 Containment Vent Header safety Injection Tank Test Line Reactor Drain Tank Pump Suction The differences between Quality Group B and C (code class 2
and 3, respectively) are mainly mainfest in the quality assurance requirements, ie, level of nondestructive examination (NDE), materials traceability, and inservice inspection.
Design code stress allowables remain unchanged as noted in FSAR Table 30A30 Section IV of this report provides a tabulation of the NDE performed for the components under consideration,.
- III, SAFETY IMPLICATIONS While no real consequence is to be expected from the improper classification of these components since code class 2 and 3
components have identical. design stress requiremetns, a deviation from stated FSAR requirements was in evidence, IV. CORRECTIVE ACTION All piping valves, fittings, field welds and shop welds associated with the aforementioned penetrations were investi-gated as a result of the upgrading effort to establish the level of NDE previously required by code class 3 of the design codes applicable to St. Lucie Unit 1 (and/or by Ebasco design
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specifications which often exceed minimum code requirements) for comparison with the level of NDE required by code class 2
Additional NDE required has of those codes (refer to Table 1).
been completed.
Records of all radiography, magnetic particle
= and/or liquid penetrant tests performed are on file at, the Ebasco site Quality Control Department..
Minor defects uncovered by NDE have. been resolved using procedures which are in accordance with the applicable codes.
All areas will be satisfactorily completed prior to fuel loading, scheduled for March 1, 1976.
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COMPARISON OF CODE CLASS 2 and 3 NDE RE UIREMENTS
- CODE CLASS 2
CODE CLASS 3
COMPONENT EBASCO SPEC 850-10 CODE
'EBASCO SPEC 850-10 CODE Seamless Piping 100%
UT weld ends LP Mat'1 Spec Mat'1 Spec Mat'1 Spec Forged Fittings Cast Fittings 100%
RT 100% LP or MT Mat'1 Spec LP or MT Static:
RT Centrifugal:
UT. to RT 100% LP or MT, Mat'1 Spec RT (to 2" from Mat'1 Spec weld end)
RT >
2 1/2" Random RT > 4" 100% Visual 100% Visual Socket Welds 2" and under LP or MT LP or MT Not Re@'d Not Req'd Branch Conn.
100%
RT > 4" Random LP or MT 4" and over Cast Valves 100%
RT 100% LP or MT RT + LP or MT RT (to 2" from
.Not req'd weld end) 100% LP or MT Forged Valves 100%
UT >
2 1/2" 100%
LP or MT Mat'.1 Spec 100% LP or MT Mat'1 Spec
- ANSI B31.7 (1969),
1968 Draft Pump 6 Valve Code, Ebasco Spec 850-10
P. O. BOX 013100, MIAMI, FLORIDA 33101
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FLORIDA POU/FII Fi L'GHT CO'-'Y February 19, 1976 L-76-61 Mr. John G. Davis, Acting Director Office of Xnspection and Enforcement U.
S. Nuclear Regulatory Commission Washington, D.
C.
20555
Dear Mr. Davis:
Re:
10 CFR 50.55(e)
Final Report Xmproper Containment Boundary Quality Group Designation St. Lucie Unit No
~
1 On January 22, 1976, I forwarded an interim report to you concerning the improper quality group designation of a number of th containment boundary penetrations at St. Lucie Unit No. l.
A final report of this incident is herewith forwarded to you, in
,accordance with 10 CFR 50.55(e).
Yours very truly,
/
C.~v+j
/
Robert E. Uhrig Vice President:
REU:nch Attachment cc:
M. S. I(idd Norman C. Moseley Jack R.
- Newman, Esq.
>>h~~ SUILO FLORIOe
FLORIDA POWER
& LIGHT COMPANY ST.
LUCIE PLANT UNIT.51 FINAL REPORT CONTAINMENT BOUNDARD QUALITY GROUP DESIGNATION
- February, 1976
I
SUMMARY
During an updating of piping and instrumentation
- diagrams, it was noted that the lines and containment isolation valves attaching to fourteen containment penetration assemblies were designated as Quality Group C.
Since these lines and their respective isolation valves comprise part of the, containment
- boundary, the appropriate quality group designation is "B" a stated in FSAR Table 3.2-1.
A review to determine the additional NDE and other QA and code requirements necessary to upgrade Quality Group C lines andvalves to Quality Group B has been performed.
The up-grading efforts are complete with no major repair work having resulted from the efforts.
II DESCRIPTION OF DEFICIENCY The following containment penetration isolation bounda'ry piping had been procured as Quality Group C in total or in part up to and including the containment isolation valves located outside containment:
PENET.
NO.
. SERVICE 14 15 i17, 19 (21 Nitrogen Supply Containment Fan Coolers Cooling Water Return 16 g 18 g 20 g 22'ontainment Fan Coolers Cooling Water Supply 23 24 Reactor Coolant Supply Reactor Coolant Return Pump Cooling Water Pump Cooling Water
PENET.
N RVICE 31 Containment Vent Header 41 safety Injection Tank Test Line Reactor Drain Tank Pump Suction The differences between Quality Group B and C (code class 2
and.,3, respectively) are mainly mainfest in the quality assurance requirements, ie, level of nondestructive examination (NDE), materials traceability,"and inservice inspection.
Design code stress allowables remain unchanged as noted in FSAR Table 3 9-3 Section IV of this report provides a tabulation of the NDE performed for the components under consideration,.
III.
SAFETY IMPLICATIONS While no real consequence is to be expected from the improper classification of these components since code class 2 and 3
components have identical. design stress requiremetns, a deviation from stated FSAR requirements was in evidence, IV, CORRECTIVE ACTION All piping valves, fittings, field welds and shop welds associated with the aforementioned penetrations were investi-gated as a result of the upgrading effort to establish the level of NDE previously required by code class 3 of the design codes applicable to St. Lucie Unit 1 (and/or by Ebasco
- design, specifications which often exceed minimum code requirements) for comparison with the level of NDE required by code class 2
I of those codes (refer to Table 1).
Additional NDE required has been completed.
Records of all radiography, magnetic particle and/or liquid penetrant tests performed are on file at the Ebasco site Quality Control Department.
Minor defects uncovered by NDE have. been resolved using procedures which are in accordance with the applicable codes.
All areas will be satisfactorily completed prior to fuel loading, scheduled for March 1, 1976.
Ct
~,
COMPARISON OF CODE CLASS 2 and 3 NDE RE9UIREMENTS
- CODE CLASS 2
CODE CLASS 3
COMPONENT EBASCO SPEC 850-10 CODE EBASCO SPEC 850-10 CODE Seamless Piping 100%
UT weld ends LP Mat'1 Spec Mat'1 Spec Mat'1 Spec Forged Fittings
'I 100%
UT 100% LP or MT Mat'1 Spec 100% LP or MT Mat'1 Spec Cast Fittings 100%
RT 100% LP or MT LP or MT Static:
RT Centrifugal:
UT. to RT RT (to 2" from Mat'1 Spec weld end)
RT >
2 1/2" Random RT > 4" 100% Visual 100% Visual Socket Welds 2" and under LP or MT LP or MT Not Req'd Not Req'd Branch Conn.
100%
RT > 4" Random LP or MT 4" and over Cast Valves 100'%T 100% LP or MT RT + LP or MT RT (to 2" from
.Not req'd weld end) 100% LP or MT Forged Valves 100%
UT >
2 1/2" Mat'.1 Spec 100% LP or MT.
- ANSI B31.7 (1969),
1968 Draft Pump a Valve Code, Ebasco Spec 850-10