ML20056A788
| ML20056A788 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/24/1990 |
| From: | Dudley R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20056A789 | List: |
| References | |
| NUDOCS 9008090199 | |
| Download: ML20056A788 (9) | |
Text
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UNITED ST ATES
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l l; NUCLE AR REGULATORY _ COMMISSION f
.s wAsmoton, o. c. nosss N.,.
p ENTERGY OPERATIONS, INC.
DOCKET NO. 50-313 ARKANSAS NUCLEAR ONE. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE-Amendment No. 134 License No. DPR-51 1.
lThe Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Arkansas Power and Light Company-(thelicensee)datedOctober 19, 1989, as supplemented by letter dated May 22, 1990, complies with the standards and requirements of the Ato.31c Energy Act of 1954, as amended (the Act), and the g
Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as b
amended, the provisions of the Act, and the rules and regulations of the Comission; C.
There-is reasonable assurance:
(1) 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 L
conducted in compliance with the Comission's regulations; L
D.
-The issuance of this license amendment will not be-inimical to the comon 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.
i 9008090.199 9007.24 PDR ADOCK 05000313 P
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:
2.
Technical Specifications The Technical Specifications-contained in Appendix A, as revised through Amendment No.134, are hereby incorporated in the license. -The licensee shall operate.the facility in accordance with the Technical Specifications.
3.
The-license-amendment is effective 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY C0tNISSION Richard F. Dudley, Acting Director Project Directorate IV-1 Division of Reactor Projects - III, IV, Y and Special Projects Office'of Nuclear Reactor Regulation
Attachment:
7 Changes to the Technical 2
' Specifications.
Date of Issuance: July 24, 1990 l.
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ATTACHMENT TO LICENSE AMENDMENT NO.134,
-a
' FACILITY OPERATING LICENSE NO. DPR-51 DOCKET NO. 50-313 I
' Revise the'following pages of the Appendix "A" Technical Specifications j
with the att6ched pages. The revised pages are identified by Amendment
,8 i
number and contain vertical lines indicating-the area of change.
e REMOVE PAGES INSERT PAGES
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27 27 i
110j 110j 110k 110k 1101 1101 110m 110m 110ml 110ml S
9.
S.1
- 3.1.6=
Leakage.
Specification 3.1.6.1 If the total reactor coolant leakage rate exceeds 10 gpm, the reactor shall be shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of; detection.
3.1.6.2 If unidentified reactor coolant leakage (exceeding normal evaporative losses) exceeds 1 gpm or if any reactor coolant leakage is evaluated as unsafe, the reactor shall be shut-down within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of detection.
3.1.6.3.a If it is determined that any reactor coolant leakage exists through a non-isolable fault in a reactor coolant system t
strength boundary (such as the reactor vessel, piping, valve body, etc., except steam generator tubes), the reactor shall be shutdown and a cooldown to the cold shutdown condition shall be initiated within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of detection.
3.1.6.3.b If the leakage through the tubes of any one steam generator equals or exceeds 500 gallons per day (0.347 gpm), a reactor l
shutdown shall be initiated within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and the reactor shall be in the cold shutdown condition within the next 30 l
l hours.
3.1.6.4 Deleted 3.1.6.5 Action to evaluate the safety implication of reactor coolant leakage shall be initiated within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of detection..The nature, as.well as the magnitude of the leak, shall be considered in-this evaluation. The safety evaluation shall assure that the exposure of offsite personnel to radiation is within the guidelines of 10CFR20.
3.1.6.6 If reactor shutdown is required per Specification 3.1.6.1, 3.1.6.2, or 3.1.6.3 the reactor shall not be restarted unt'1 the leak is repaired or unti.1 the problem is otherwise corrected.
3.1.6.7 When the reactor is at power operation, three reactor cool-ant leak detection systems of different operating principles
.shall be in operation.
One.of these systems is sensitivs to radioactivity and consists of a' radioactive gas detector and an air particulate activity. detector.
Both of these'instru-ments may be out-of-service simultaneously for a period of no more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided two other means are available to l
detect leakage and reactor building air samples are taken and analyzed in the laboratory-at least once per shif t; other-wise, be in at least Hot Standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in Cold Shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
3.1.6.8 Loss of reactor coolant through reactor coolant pump seals and system valves to connecting systems which l
i l-Amendment No. 57 IIE, II2, 134 27
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4'.18 STEAM GENERATOR TUBING SURVEILLANCE
- A'oplicability.
Applies'to the surveillance of tubing of each steam generator.
Objective To ensure integrity of the steam generator tubing through a defined inservice surveillance program, and to minimize 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 Methods a.
Inservice inspection of steam generator tubing shall include-non-destructive examinaticn by eddy-current testing or other equivalent techniques.
The inspection 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 except for a sleeved tube at the lower sleeve end, b.
For examination of the sleeved steam generator tubing at the lower sleeve end, the indications wil1~be compared to those J
obtained during the baseline sleeved tube inspection.
I Significant deviations between these indications will be considered sufficient evidence to warrant-designation as a degraded tube.
Direct quantification of the 40 percent through-wall plugging limit is available with eddy-current testing.
4.18.3 Selection and Testina The steam generator sample size is specified in Table 4.18-1. 'The steam-I generator tube minimum sample size, inspection result classification, and the corresponding action required shall be as specified in Table 4.18-2.
I 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 j
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:
Amendment No. 24, AZ, SE, ISE,134 110j
m 4.
1,.
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.A tube inspection (pursuant to Specification 4.18.5.a.9) shall be j
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.
'3.
Tubes in the following groups may be excluded from the first random sample if all tubes in a group in both steam generators are inspected.
The inspection 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 will be subjected to the random inspection.
(1). Group A-1: Tubes within one, two or three rows of the open inspection lane.
(2) G oup A-2:
Unplugged tubes with sleeves installed.
(3) ( oup A-3:
Tubes in the wedge-shaped group on rfther side of the lane region (Group A-1) as efined by Figure 4.18.1.
e b.
The second and third sample inspections during each inservice inspection as required by Table 4.18-2 may be less tha'n a full I
tube inspection by concentrating the inspection on those areas of the tube sheet array and on those portions of the tubes where tubes 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 Less than 5% of the total tubes inspected are degraded tubes
.c and none of,the' inspected tubes are defective.
C-2 One or more tubes, but not more i
than 1% of the total tubes i
inspected, are defective, or between 5% and 10% of the total tubes inspected are degraded tubes.
C-3 More than 10% of the total tubes inspected are degraded i
tubes or more than 1% of the inspected tubes are defective.
Amendment No. 2#, #2, 85, ISE, 134, 110k
NOTES:
(1)
In all: inspections, previously degrad:d tubes whoso
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-degradations have not been spanned by a sleeve aust exhibit significant-(>10%) further wall penetrations to be' included in the above percentage calculations.
(2) Where special inspections are performed pursuant'to 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 determining the Inspection Results Category for the i
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 not 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 l
for a given group
- of tubes fall in Category C-3, subsequent inservice inspections shall be performed at intervals of not less than 10 nor more than 20 calendar months after the previous inspection.
The increase in inspection frequency shall apply 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 samp1'e inspection specified in Table 4.18-2 during the shutdown j
subsequent to any of the following conditions:
1.
Primary-to-secondary leakage in excess of the limits of l
Specification 3.1.6.3.b (Inservice inspection not required if p
leaks originate from tube-to-tubesheet welds.
If the leaking tube is from either Group A-1 or A-3 as defined in l..
Specification 4.18.3.a.3, all of the tubes in the affected l
group in this steam generator may be inspected in lieu of 1
- 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.
l Amendment No. '24, #2, 88, 208,134 1101
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- 1 the-first sample inspection specified in Table 4.18-2.
If the degradation mechanism which caused-the leak-is limited to a specific portion of the tube length, the. inspection per
-this' paragraph may be limited to the affected portion of the i
tube length.
If the results of this : inspection fall into the C-3 category, all of the tubes in the same group in the other steam generator will also be similarly inspected.)
2.
A seismic occurrence greater'than the Operating Basis Earthquake, 3.
A loss-of-coolant accident requiring actuation of the engineered safeguards, or i:
l 4.
A main steam line or feedwater line break.
4.18.5 Acceptance Criteria s.
As used in this specification:
L 1.
Tubing or Tube means that portion of the tube or sleeve which forms the primary system to secondary system pressure l
boundary.
I 2.
Imperfection means an exception to the dimensions, finish or l
contour of a tube from that required by fabrication drawings t
or specifications.
Eddy current testing indications below l
20% of the nominal tube wall thickness, if detectable, may be considered as imperfections.
3.
Dearadation means a service-induced cracking,
wastage, wear or general corrosion occurring on either the inside or outside-of a tube.
4.
Dearaded Tube means a tube containing imperfections 5 20% of the nominal wall thickness caused by degradation, except u
where all degradation has been spanned by the installation L
of a sleeve.
5.
% Dearadation means the percentage of the tube wall thickness affected or removed by degradation.
6.
Defect means an imperfection of such severity that it exceeds the plugging limit except where the imperfection T
has been spanned by the installation of a sleeve.
A tube L
containing-a defect in its pressure boundary is defective.
t L
7.
Plugaino Limit means the imperfection depth at or beyond-L which the tube shall be restored to serviceability by the installation of a sleeve or removed from service because it L
may become unserviceable prior to the next inspection; it is equal to 40% of the nominal tube wall thickness.
l i.
Amendment No. 24, AZ, 86, ISE,134 110m
8.
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.
9.
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 or sleeve all tubes exceeding the plugging limit and all tubes containing through-wall cracks) required by Table 4.18-2.
Amendment No. 24, AI, 86, ISS, 134 110ml