ML20006E992
| ML20006E992 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 02/15/1990 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20006E988 | List: |
| References | |
| NUDOCS 9002270049 | |
| Download: ML20006E992 (8) | |
Text
_.. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
U.S. Jiiclear. Rig 51ctcry Comuniocica i ATTN:. Document C ntrol Dsck
( Fcbrbzry. 15,'1990--
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- Attcchment No. 2;
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+g REACTOR COOLANT SYSTEM:
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13/4.4.5 STEAM GENERATORS-k LIMITING CONDITION FOR OPERATION 3.4.5 Each steam generator shall be OPERABLE.
AFPLICABILITY:
MODES 1, 2, 3 and 4 ACTION:
With one or more steam generators inoperable, restore the inoperable generator (s) to OPERABLE status prior to increasing T,yg above 200*F.
SURVEILLANCE REQUIREMENTS 4
4.4.5.0 Each steam generator shall be demonstrated OPERABLE by performance of-the following. augmented inservice inspection program and the requirements of Specification 4.0.5.
4.4.5.1 Steam Generator Sample Selection and Inscection - Each steam generator shall-be oetermined OPERABl.E during snutoown by seiecting and inspecting'at
.least the Linimum' number of steam generators specified-in Table 4.4-1.
4.4.5.2 Steam Generator Tube Sample Selection and Inspection - The steam generat.or tube minimum. sample size, inspection result classification,.and the R
corresponding action _ required-shall be as specified in Table 4.4-2.
The:
inservice inspection of steam generator tubes shall be performed at the fre-quencies'specified in Specification 4.4.5.3 and_the inspected tubes'snall:be-verified acceptable per the acceptance criteria of Specification 4.4.5.4.
The tubes selected for each inservice inspection shall include at least 3% of the total number of tubas in all steam generators;.the tubes selected for.these l
inspections shall be selected-on a random basis except:
Whereexperienceinsimilarplantswithsimilarwaterchemistry a.
indicates critical areas to be inspected, then at least 50% of the tubes inspected shall be from these critical areas; V
b.
The first skmple 'of tubes selected for each inservice inspection
/l (subsequent to the preservice inspection) of each steam generator shall include:
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McGUIRE - UNITS 1 and 2-3/4 4-11
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= SURVEILLANCE REQUIREMENTS (Continued) 1)
'All nonplugged tubes that previously had detectable wall penetrations (greater than 20%),
2)
- Tubes in those. areas where experience has indicated potential problems, and r
3)
A tube inspection (pursuant-to Specification 4.4.5.4.a.8) shall
'1
- be performed on each selected tube., If any selected tube does not permit'the passage of the eddy current probe for a tube inspection, this.shall be recorded and an adjacent tube shall be selected and subjected to a tube inspection.
c.
In addition to the 35 sample, all F* tubes will be inspected.
d.
The tubes selected as the second and third. samples (if required by--
l Table 4.4-2) during each inservice inspection may be subjected to a partial tube inspection provided:
'1)
The tubes selected for these samples include the tubes from those~ areas of the tube sheet array where tubes with imperfections were previously found, and-2)-
The inspections. include those portions of the tub (s where imperfections were previously found.
The results of each sample inspection shall be classified into one of-the following three categories:
Category Inspection Results C-1 Less than 5% of the total tubes inspected are degraded tubes and none-of the inspected tubes are defective.
L C-2 One or more tubes, but not more than 1% of the total-tubes inspected are defective, or between 5% and 10% of the total tubes inspected are degraded tubes.
i C-3 More than 105 of the total tubes inspected are degraded tubes or more than 1% of the inspected tubes are defective.
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Note:
In all inspections, previously degraded tubes must exhibit I
significant (greater than 10%) further wall penetrations to be included in the above percentage calculations.
- McGUIRE - UNITS 1 and 2 3/4 4-12 Amendment No. 59 (Unit 1)
Amendment No. 40(Unit 2)
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SURVEll. LANCE REQUIREMENTS (Continued)
- )
4.4.5.3~ Inspection Frecuencies - The above required inservice. inspections of steam generator tubes shall be performed at.the following frequencies:
a.
The first inservice inspection shall be performed after 6 Effective Full Power Months but within 24 calendar months.of initial criticality.-
Subsequent inservice inspections shall be performed at intervals of J
not less than 12 nor more than 24 calendar months after the previous inspection.
If two consecutive inspections following service under AVT conditions, not including the preservice inspection, result in L
all' inspection results falling into the C-1 category or if two consecutive inspections demonstrate that previously observed degra-dation has not continued and no additional degradation has occurred, l
the inspection interval may be extended to a maximum of once per 40 months; b.
If the results of the-inservice inspection of a steam generator =.
conducted in accordance with Table 4.4-2 at 40-month intervals fall in Category C-3, the inspection frequency shall be increased to at least once-per 20 months.
The increase in inspection frequency shall apply until_.the subsequent inspections satisfy the criteria of
. Specification 4.4.5.3a; the interval may then be extended-to a maximum of once per 40 months; and p'
c.
Additional, unscheduled inservice inspections'shall be performed on t
each steam generator in accordance with the first: sample inspection specified'in Table 4.4-2 during the shutdown subsequent to any of.
the following conditions:
1)
Reactor-to-secondary tubes leaks (not including leaks originating l,
from tube-to-tube sheet welds) in excess of the limits of Specification 3.4.6.2, l
2)
A seismic occurrence greater than the Operating Bosis Earthquake,.
l, 3)
A loss-of-coolant accident requiring actuation of the Engineered-Safety Features, and l
4)
A main steam line or feedwater line break.
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- McGUIRE - UNITS 1 and 2 3/4 4-13
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U;By Oce' $ar R2gulatery Commismien i
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' ATTN:^. Document Cantrol Dask-Fabruhry 15, 19907 J Attechnent No. 2:
REACTOR COOLANT SYSTEM-SURVEILLANCE REQUIREMENTS (Continued) l i
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4.4.5.4 Acceptance Criteria a.
~As used in this specification: y g,,
i 1)
Imperfection means n exception to the dimensions, finish or contour of a tube rom that required by fabrication drawings or specifications.
Eddy-current testing indications below 20% of the nominal tube wall thickness, if detectable, may be'consid-ered as imperfect
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j 2)
Deoradation means a-service-induced cracking, wastage, wear or general co rosion occurring on either inside or outside of a tubejer s4deod,;
3)
DearadedTubemeansatubeIco IIingimperfectionsgreater than or equal to 20% of the nomina 1 wall thickness caused by i
9 degradation;
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er slears s
4)
% dearadation means the percentage of the tube wall thickness f
d affected or removed by degradation; j
5)
Defect means an imperfection of such severity that it exceeds s
the m ;; % 11mit.
Atube4c,onj*ainingadefectisdefective; y',.
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hy p/appby e n,emd &
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- 6).
-__ h Limit means the imperfection d th at or beyond which d**Waf' the tub hall-be removed from service and is equal to 40% of I
ominal tub well-thickness.- This definition does not apply oc sleeve to the-the tubesheet region below the F*-distance pro-vided the tube is not degraded (i.e., no indications of crack -
ing) within the F* distance. p er slama.
7)
Unserviceable describes th condition of a tube ^if it leaks or.
contains a defect large ough to affect its structura1Linteg-4 rity in the event of a Operatini Basis Earthquake, a loss-of-coolant accident, or steam line or feedwater line' break as specified in 4.4.
c, above; 8)
Tube Inspecti means an inspection of the steam generator tube from the p nt of entry (hot leg side) completely around the U-bend the top support of the c.old leg; and zf a Ma 4 deved due 4 dyud* Ash 'A f"
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McGUIRE - UNITS 1 and 2 3/4 4-14 Amendment No. 24 a(Unit 1) 84
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= U.S. Nuciccr R33ulctcry Comuniositu DATTN Document Contrr,1 De k.-
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SURVEILLANCE REQUIREMENTS (Continued)-
9)
Preservice Inspection means an inspection of the full length of j
each tube in each steam generator performed by eddy current.-
techniques prior to service to establish a baseline condition of the tubing.
This inspection shall be performed after the field hydrostatic test and-prior to initial POWER OPERATION using the equipment and techniques expected to be used during subsequent insarvice inspections.
10)
F* Distance is the distance into the tubesheet from the top face of the tubesheet or the top of the last hardroll, whichever is lower (further into the tubesheet) that has been conservatively chosen to be-2 inches.
11)' F* TUBE is a tube with degradation equal to or greater than 40%,
below the F* distance and not degraded (i.e., no indications of cracking) in the F* distance.
t b.-
The steam generator shall be determined OPERABLE after completing the
. corresponding actions (pluga ll: tubes exceeding the ph;;;t;, limit a
f
-and all tubes containing th ough wall cracks) required by reple-y, Table 4.4-2.
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4.4.5,5 Reports Within~15 days following the completion of each inservice inspection a.
of steam generator tubes, the number of tubes plugged in each steam generator shall be reported to the Commission in a Special Report
-pursuant to Specification 6.9.2; b.
The complete results of.the steam ' generator tube inser.vice inspection 4
shall be submitted to the Commission in a Special Report pursuant to Specification 6.9.2 within 12 months following the completion of the inspection.
This Special Report..shall include:
1)
Number and extent of tubes inspected, 2)
Location and percent of wall-thickness penetration for each indication of an imperfection, and 3)
Identification of tubes plugge4 se rep 'r <d.
I The results of inspections of F* tubes shall be reported to the c.
Commission in,a report, prior to the restart of the unit following the inspection.
This report shall include:
1)
Identification of F* tubes, and
-2)
Location and size of the degradation.
McGUIRE -' UNITS 1 and 2-3/4 4-15 Amendment No. M (Unit 1) y
lU.S.il!rclear Regulatory Commission c AT111:' D:cument Centrol Deck-
)Fobru ry 15, 1990
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'_ Attachment No. 2 3
. BASES 3/4.4.4 RELIEF VALVES
. The power-operated relief valves (PORVs) and steam bubble function to relieve RCS. pressure during all design transients up to and including the design step load decrease with steam dump.
Operation of the PORVs minimizes the undesirable opening of the spring-loaded pressurizer code safety valves.
.Each PORY has a remotely operated block valve to provide a positive shutoff capability should a relief valve become inoperable.
3/4.4.5~ STEAM GENERATORS The Surveillance Requirements for inspection of the steam generator tubes-ensure that the structural integrity of _ this portion of the RCS will be main-tained. -The program.for inservice inspection of steam generator tubes is based on= a modification of Regulatory Guide 1.83, Revision 1.
Inservice inspection of: steam generator tubing is essential in order to maintain surveillance of the conditions of the tubes in the event that there is evidence of mechanical. damage or progressive degradation-due to design, manufacturing errors, or inservice conditions that lead to corrnsion.
Inservice inspection of steam generator tubing also provides a a uns of characterizing the nature and cause of any tube degradation so that corrective measures can be taken. c g.
,74 r.4,, A A d4,44 The plant is-expected to be operated in a manner such that the secondary
-coolant will be maintained within those chemistry limits found to result in negligible corrosion of the steam generator tubes.
If the secondary coolant chemistry is not. maintained within these limits, localized corrosion may likely_' result in stress corrosion cracking.
The extent of cracking during-plant operation would be limited by the-limitation of steam generator tube-leakage between the Reactor Coolant System and the Secondary Coolant System
-(reactor-to-secondary leakage = 500 gallons per day.per steam generator).
Cracks having a reactor-to-secondary leakage less than this limit during:
operation will have an adequate margin of safety to withstand the loads
-imposed during normal operation and by postulated accidents.
Operating plants
_have demonstrated that reactor-to-secondary leakage of 500 gallons per day per steam generator can readily be detected by radiation monitors of steam generator blowdown.
Leakage-in excess of this limit will require plant shutdown and an unscheduled inspection, during which the leaking tubes will be located and plugged, or 1leeva j @ygg Jell be.
Wastage-type defects are un ikely wit proper chemistr treatment of the-secondary coolant.
However, even if a de ect should devel p in service, it will be found during scheduled in1ervic steam generator ube examinations.
Rap ir" hg;' ; will be required for all tubes with imperfectio s exceeding the repaikk;;;h; limit of 40% of the tube" nominal wall thicknes.
Steam generator tube inspections of operating plants have demonstrated e capability to
(:
reliably detect wastage. type degradation that has pen rated 20% of the origi-t nal tube wall thickness.
For tubes with degradati below the F* distance, and not degraded within the Fa distance,ypl,.ggi-is not required,t.rn u d N 'i O 7
fromakket fT-1 M *"Y I Amendment nom (Unit 1)
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McGUIRE - UNITS 1 and 2 8 3/4 4-3 Amendment No M(Unit 2)
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,U.S. Nuclear Regulatory Commission ATTN Document Control Desk b
February 15, 1990 Attachment No. 2 Bases, 3/4.4.5,-Steam Generators, Insert Item A:
s V
L Inservice inspection of steam generator sleeves is also required to ensure RCS integrity. The B&W process (or method) equivalent to the inspection method described in Topical Report BAW-2045(p)-A will be used.
State of the art processes will be considered.-
)
N Bases, - 3/4.'4.5, Steam Generators, Insert Item B Defective steam generator tubes can be repaired by the installar. ion of i
-sleeves which span the area of degradation, and serve as a replacement pressure boundary for the' degraded portion of the tube, allowing the tube to remain in service.
Bases, 3/4.4.5, Steam Generators, Insert Item C:
If a tube is sleeved due to degradation in the F* distance,;then any defects in the tube below the sleeve will remain in service without repair.-
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h REACTOR-COOLANT SYSTEM BASES-i STEAM GENERATORS (Continued)
Whenever:the results'of any steam generator tubing inservice inspection fall into Category C-3, these results will be promptly reported to the Commission pursuant to 10 CFR Sections 50.72 and 50.73 prior to resumption of plant operation.
Such cases will be considered by the Commission on a case-
[
by-case basis and may result in a requirement for analysis, laboratory exami-natib 9, tests, additional eddy-current inspection, and revision of the.
~ Techr.h.al Specifications, if necessary.
_s 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE 3/4.4.6.1 LEAKAGE DETECTION SYSTEMS The RCS Leakage Detection Systems required by this specification are provided to monitor and detect leakage from the reactor coolant pressure boundary..These Detection Systems are consistent with the recommendations of Regulatory Guide 1.45, '" Reactor Coolant Pressure Boundary Leakage Detection Systems," May 1973.
3/4.4.6.2 OPERATIONAL LEAKAGE Industry experience has shown that while a limited amount of-leakage is expected from the RCS, the unidentified portion of this leakage can be reduced -
to a threshold value of less than 1 gpm.
This threshold value is sufficiently low to ensurs early detection of additional leakage.
The Surveillance Requirements for RCS pressure isolation valves provide added assurance of valve integrity thereby reducing the probability of gross valve failure and consequent intersystem LOCA.
Leakage from the RCS pressure isolation valves is_ IDENTIFIED LEAKAGE and will be considered as a portion of the allowed limit.
The 10 gpm-IDENTIFIED LEAKAGE limitation-provides allowance for a limited amount of leakage from known sources whose presence will not' interfere with the detection of UNIDENTIFIED LEAKAGE by the Leakage Detection Systems.
The CONTROLLED LEAKAGE limitation restricts operation when the total flow supplied to the reactor coolant pump seals exceeds 40 gpm with the modulating valve in the supply line fully open at a nominal RCS pressure of 2235 psig.
This_ limitation ensures that in the event of a LOCA, the Safety Injection flow
.will not be less than assumed in the accident analyses.
The total steam generator tube leakage limit of 1 gpm for all steam
. generators not isolated from the RCS ensures that the dosage contribution frotr.
the tube leakage will be limited to a small fraction of 10 CFR Part 100 dose guideline values in the event of either a steam generator tube rupture or staam line break.
The l gpm limit is consistent with the assumptions used in the analysis of these accidents.
The 500 gpd leakage limit per steam generator entures that steam generator tube integrity is maintained in the event of a main steam line rupture or under LOCA conditions.
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- McGUIRE ' UNITS 1 and 2 8 3/4 4-4 Amendment No.52(Unit 1)
Amendment No.33(Unit 2)