ML20108A330
| ML20108A330 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 11/08/1984 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Arkansas Power & Light Co |
| Shared Package | |
| ML20108A333 | List: |
| References | |
| DPR-51-A-086 NUDOCS 8411140540 | |
| Download: ML20108A330 (13) | |
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[$.Q([o UNITED STATES g
klf NUCLEAR REGULATORY COMMISSION 5
WASHINGTON, D. C. 20555 V
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,e ARKANSAS POWER & LIGHT COMPANY DOCKET N0. 50-313 ARKANSAS NUCLEAR ONE, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE
- Amendment No. 86 License No. DPR-51 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Arkansas Power and Light Company (the licensee) dated August 13, 1984, complies with the standards t
and requirements of the Atomic Energy'Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission;.
C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of'the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendmeni: sill not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.c.(2) of Facility Operating License No. DPR-51 is hereby amended to read as follows:
I 8411140540 841108 PDR ADOCK 05000313 P'
O-s Technical Specifications The Technical Specifications contained.in Appendices.
A and B, as revised through Amendment No. 86 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the
-Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULSTORY COMMISSION A
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. Stolz, Chief
- Spe ting Reactors Branc6 #4 Di 1sion of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 8, 1984 t
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ATTACHMENT TO LICENSE AMELDMENT NO. 86 FACILITY OPERATING LICENSE N0. OPR-51 DOCKET NO. 50-313 Replace the following pages of the'Appendfx "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain; vertical lines indicating the area of change.
Remove ts. sert v
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vi.
110j 110j 110k 110k 1101 1101 110m 110m 110n 110n 1100 1100 11001
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.3 3.5.2-2E R00 POSITION' LIMITS FOR TWO-PUMP OPERATION-FROM 0 to 60 EFPD-ANO-1, CYCLE 5 48c4 3.5.2-2F R0D POSITION LIMITS FOR TWO-PUMP OPERATION FROM 50 to 200 10 EFPD-ANO-1,- CYCLE 5 48c5 3.5.2-2G R0D POSITION LIMITS FOR TWO-PUMP OPERATION FROM 200 10 T0.
400 10 EFPD-AN0-1, CYCLE 5
-48c6 3.~ 5. 2-2H R0D POSITION LIMITS FOR TWO-PUMP OPERATION FROM 400 10 TO 435 10 EFPD-ANO-1, CYCLE 5 48c7 3.5.2-3A OPERATIONAL POWER IMBALANCE ENVELOPE FOR OPERATION FROM 0 T0 60 EFPD-ANO-1, CYCLE 5 48d 3.5.2-3B OPERATIONAL' POWER IMBALANCE ENVELOPE FOR OPERATION FROM 50 TO 200 10 EFPD-ANO-1, CYCLE 5 48d1 3.5.2-3C OPERATIONAL POWER IMBALANCE ENVELOPE FOR OPERATION FROM 200 10 TO 400 10 EFPD-ANO-1, CYCLE 5 48d2 3.5.2-30 OPERATIONALPOWERIMBALANCEENVELOPEIOROPERATIONFROM400 10 TO 435 10 EFPD-AN0-1, CYCLE 5 48d3 3.5.2-4 LOCA LIMITED. MAXIMUM ALLOWABLE LINEAR HEAT RATE' 48e.
- 3.5.2-4A ASPR POSITION LIMITS FOR OPERATION FROM 0 to 60 EFPD-ANO-1, CYCLE 5 48f' 3.5.2-4B ASPR POSITION LIMITS FOR OPERATION FROM 50 to 200 10 EFPD-AN0-1, CYCLE 5 48g 3.5.2-4C APSR POSITION LIMITS FOR OPERATION FROM 200 10 to 400 10 EFPD-AN0-1, CYCLE 5 48h 3.5.2.4C APSR POSITION LIMITS FOR OPERATION FROM 400 10 to 435 10 EFPD-ANO-1, CYCLE 5 48i 3.5.4-1 INCORE INSTRUMENTATION SPECIFICATION AXIAL IMBALANCE INDICATION 53a 3.5.4-2 INCORE INSTRUMENTATION SPECIFICATION RADIAL FLUX TILT l
INDICATION 53b 3.5.4-3 INCORE INSTRUMENTATION SPECIFICATION 53c 4.4.2-1 NORMALIZED LIFT 0FF FORCE - HOOP TENDONS 83b 4.4.2-2 NORMALIZED LIFT 0FF FORCE - DOME TENDONS 85c.
4.4.2-3 NORMALIZED LIFT 0FF FORCE - VERTICAL TENDONS 85d v
Amendment fic. E7, S$,86
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.4.18.12 UPPER TUBE _ SHEET VIEW 0F.SPECIAL GROUPS PER SPECIFICATION 4.18.3.a.3'
-110o2 1:'
6.2-1 MANAGEMENT ORGANIZATION: CHART 119
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FUNCTIONAL, ORGANIZATION FOR PLANT OPERATION 120 4
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i vi-Amendment No. 86
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4.18 STEAf4 GENERATOR TUBING SURVEILLANCE Applicability-Applies to the surveillance of tubing of each steam generator.
Objective To ensure integrity of the steam yens ator tubing through a defined inservice surveillance program, and to
- nimize exposure of personnel to radiation during performance of the surveillance program.
Specification 4.18.1 Baseline Inspection The first steam generator tubing inspection performed according to Specifications 4.18.2 and 4.18.3.a shall be considered as constituting the baseline condition for subsequent inspections.
4.18.2 Examination tiethods Inservice inspection of steam generator tubing shall include nondestructive-examination by eddy-current testing or other equivalent techniques.
The in-spection equipment shall provide a sensitivity that will detect defects with a penetration of 20 percent or more of the minimum allowable as-manufactured tube wall thickness.
.4.18.3 Selection and Testing The steam generator sample size is specified in Table 4.18.1.
The steam generator tube minimum sample size, inspection result classification, and the corresponding action required shall be as specified in Table 4.18.2.
The inservice inspection of steam generator tubes shall be performed at_the frequencies specified.in Specification 4.18.4 and the inspected tubes shall be verified acceptable per the acceptance criteria of Specification 4.18.5.
The tubes selected for each inservice inspection shall include at least 3%
of the total number of tubes in both steam generators; the tubes selected for these inspections shall be selected on a random basis except:
.a.
The first sample inspection during each inservice inspection (sub-sequent to the baseline inspection) of each steam generator shall include:
1.
All nonplugged tubes that previously had detectable wall penetrations (>20%), and 2.
At least 50% of the tubes inspected shall be in those areas where experience has indicated potential problems, except where specific groups are inspected per Specification 4.18.3.a.3.
Amendment No. 24, A7, 86 110j
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A-tube inspection'(pursuant to Specification 4.18.5.a.8) shall be 1
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.
I 3.
Tubes in the following groups may be excluded from the first j
. random sample if all tubes in a group in both steam generators are inspected.
The inspectio'n may be concentrated on those portions of the tubes where imperfections were previously found.
No credit will be taken for these tubes in meeting minimum sample size requirements.
Where only a-portion of the. tube is inspected, the remainder of the tube
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will be subjected to the random inspection.
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(1) Group A-1:
Tubes within one, two or three rows of the open inspection lane.
(2) Group A-2: deleted (3) Group A-3:. Tubes in the wedge-shaped group on either side of the lane region (Group A-1) as defined by Figure 4.18.1.
b.
The second and third sample inspections during each inservice in-spection as required by Table 4.18.2 may be less than a full tube inspection by concentrating the. inspection on those areas of the tube sheet array and on those portions of the tubes where tubes l
with 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 f
Less than 5% of the total tubes inspected are degraded tubes and none of the in-spected tubes are defective.
C-2 One or more tubes, but not more than 1%
of the total tubes inspected, are de-fective, or between 5% and 10% of the total tubes inspected are degraded tubes.
C-3 More than 10% of the total tubes in-spected are degraded tubes or more than 1% of the inspected tubes are defective.
Amendment No. 2#, JJ, 86 110k
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'(1) LIn-all inspections, previously degraded tubes must
. exhibit significant (>10%) further wall penetrations to be included in the above percentage calculations.
(2)-Wherespecialinspectionsare'perf[rmedpursuantto 4.18.3.a.3,. defective or degraded tubes found as a result of the inspection shall be included in determining the Inspection Results Category for that special inspection but need not'be included in i
determining the Inspection Results Category for the general steam generator inspection.
4.18.4 Inspection. Intervals
.The above-required inservice inspections of steam generator tubes.shall be performed at the following frequencies:
a.
The baseline inspection shall be' performed during the first-refueling shutdown.
Subsequent inservice inspections shall be performed at intervals of not less than 10 nor more than 24 calendar months after the previous inspection.
If the results of two consecutive inspections for a given group
- of tubes following service under all volatile treatment (AVT) conditions fall into the C-1 category or if two consecutive inspections demonstrate that previously observed degradation has r.at continued and no additional degradation has occurred, the inspection interval for that group may be extended to a maximum of 40 months.
b.
If the results of the inservice inspection of a steam. generator performed in accordance with Table 4.18.2 at 40-month intervals for a given group
- of tubes fall in Category C-3, subsequent inservice inspections shall be performe,d at intervals of not less than 10 nor more than 20 calendar months after the previous inspection.
The increase in inspection frequency shall apply 4
until a subsequent inspection meets the conditions specified in 4.18.4.a and the interval can be extended to 40 months.
c.
Additional unscheduled inservice inspections shall be performed on each steam generator in accordance with the first sample inspection specified in Table 4.18.2 during the shutdown sub-sequent.to any of the following conditions:
1.
Primary-to-secondary leakage in excess of the limits of Specification 3.10 (inservice inspection not required if leaks originate from tube-to-tubesheet welds),
2.
A seismic occurrence greater than the Operating Basis Earthquake,
- A group of tubes means: (a) All tubes inspected pursuant to 4.18.3.a.3, or (b) All tubes in a steam generator less those inspected pursuant to 4.18.3.a.3.
i Amendment No. 7#, A7,86 1101
3.
LAloss-of-coolantaccidentrequiring.actuationofthe engineered safeguards, or
'4.
A main steam line or feedwater line break 4.18.5 Acceptance Criteria a.
As used'in this specification:
l1.
Imperfection means an exception to the dimensions, finish or contour of a tube from that' required by fabrication drawings or specifications. -Eddy. current testing indications below 20% of the nominal. tube wall thickness,-if detectable, may be considered as imperfections.
2.
Degradatiod means a service-induced cracking, wastage, wear i
or general corrosion occurring on either,the inside or outside of a tube.
1 3.
Degraded Tube means a' tube containing imper'fections 2 20% of
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the nominal wall thickness caused by degradation.
4.
% Degradation means the percentage of.the tube wall thickness affected or removed by degradation.
S.
Defect means an imperfection of such severity that it exceeds the plugging limit.
A tube containing a defect is defective.
6.
Plugging Limit means the imperfection depth at or beyond which the tube shall be removed from service because it may become unserviceable prior to the next inspection; it is equal to 40% of the nominal tube wall thickness.
7.
Unserviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its-structural integrity in the event of an Operating Basis Earthquake, a loss-of coolant accident, or a. steam line or feedwater line break as specified in Specification 4.18.4.c.
8.
Tube Inspection means an inspection of the steam generator tube from the point of entry completely to the point of exit.
b.
The steam generator shall be determined operable after completing the corresponding actions (plug all tubes exceeding the plugging limit and all tubes containing through wall cracks) required by Table 4.18.2.
Amendment tio. 7#,-#7, 86 110m
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. -f-4.18.6
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Following each i service inspection of: steam generator. tubes, the compl e
results of 'the inspection shall be reported to th'e NRC.- This report, to be subm,itted within 45 days of inspection ~ completion, shall include:
-a.
Number and extent of tubes inspected; ti.
. Location 'and. percent of wall-thickness penetration for each--
indication of an imperfection; and Identification'of tubes plugged.
c.
This report shall'be in addition to theLreport of results o'f steam generator s
tube inspections which fall into Category C-3 and which require prompt notification of the NRC per Specification 6.12.3.
Bases The surveillance requirements for inspection of the steam generator tubes ensure that'the structural integrity of this portion of the RCS will be maintained. The program for inservice inspection of steam generator tubes.is i
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 evidencelof mechanical. damage or progressive degr'adation due to design, manufacturing errors, or inservice conditions that lead to corrosion.
4 Inservice inspection of-steam generator tubing also provides a means of characterizing the nature and cause of any tube degradation so that-corrective measures can be taken.
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-Amendment No. 77, JJ, 86 110n
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-TABLE 4.18-1 MINIMUM. NUMBER OF STEAM GENERATORS TO BE' INSPECTED-DURING INSERVICE INSPECTION Preservice Inspection No No.-of_ Steam Generators per Unit Two First Inservice Inspection Two Second & Subsequent Inservice Inspections Onel Table Notation:
4 1
The inservice inspection may be limited to one steam generator on alternatico schedule encompassing 3 N % of the tubes (where N is the number of steam generators in the plant) if the results iof the first or previous inspections indicate that all steam generators are performing in a like manner.
Note that under some circumstances, the operating concitions in one or more steam generators may be found to be more severe than those in other steam generators.-Under such circumstances the sample sequence shall be modified to inspect the most severe conditions.
Amendment No. 77, SG 1100
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~ it TABLE 4.18-2 STEAM GENERATOR TUBE INSPECTION 2, 3
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l 1ST SAMPLE INSPECTION ll 2ND SAMPLE INSPECTION ll 3RD SAMPLE INSPECTION l
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Sample Size l Result Action Required ll Result l Action Required ll Result l Action Required l
l l
ll l
ll l
1 0,
l A minimum of l
C-1 l
None ll N/A l
N/A ll N/A N/A l
l S Tubes per l
l ll l
ll l
g l S.G.2 l
C-2 l Plug defective ll C-1 None ll N/A N/A l
l l
l tubes and inspect ll ll C-1 None l
l l
l additional 20 ll C-2 l Plug defective ll C-2 1 Plug defective l
l l
l tubes in this S.G.ll l tubes and inspect ll l tubes l
l l
l ll l additional 4S ll C-3 l Perform action forl l
l l
ll tubes in this SG ll l C-3 result of-l l
l l
ll C-3 Perform action forll first sample l
l l
l ll l C-3 result of ll l
l l
l ll first sample ll N/A N/A l
l-l C-3 l Inspect all tubes ll Other ll l
l l
l in this S.G plug ll S.G. isl None ll N/A l
N/A l
l l
l defective tubes ll C-1 ll l
l l
l and inspect 25 ll Other Perform action forll l
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l l tubes in other ll S.G. isl C-2 results of ll N/A l
N/A l
S l
l l S.G.
ll C-2 l second sample ll l
l l
l ll Other l Inspect all tubes ll l
l l
l Prompt notifica-ll S.G. isl in each S.G. and ll N/A l
N/A l
l l
l tion.to NRC pur-Il C-3 l plug defective ll l
l l
l l suant to specifi-ll l tubes.
Prompt ll l
l-l l
l cation 6.12.3.
ll l notification to ll l
l l
l l
ll l NRC pursuant to ll l
l-l l
l ll l specification ll l
l*
l l
l ll l 6.12.3, and re-ll l
l l
l l
ll l quest NRC approval ll l
l l
l l
ll l of remedial action ll l
l I=3-hWhereNisthenumberofsteamgeneratorsintheunit,andnisthenumberofsteam NOTES:
S generators inspected during an inspection.
2For tubes inspected pursuant to 4.18.3.a.3:
No action is required for C-1 results.
For C-2 l
results in one or both steam generators plug defer.tive tubes.
For C-3 results'in one or both steam generators, plug defective tubes and provide prompt notification of NRC parquant to specification 6.12.3.
3As part of a steam generator sleeving qualification program up to 10 demonstration sleeves'may be installed in defective tubes in lieu of.plu0ging during the sixth ANO-1 refueling.
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i FI(3URE di.1El.1.
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Upper Tube Sheet View of Special Groups per Speci,fication 4.18.3.a.3 9
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4 Plot Character Description Tube Count l
L Group A-1:
Lane region tube 382 X
Group A-3:
Wedge adjacent to lane 4831 Support rod location NA l
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l Amendment No. 86:
11002
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