ML20216D728
| ML20216D728 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/10/1998 |
| From: | William Reckley NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20216D733 | List: |
| References | |
| NUDOCS 9804150415 | |
| Download: ML20216D728 (10) | |
Text
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.Mr. C. Randy Hutcinson
. Entergy Operations, Inc.
Arkansas Nuclear One, Unit 1
- cc:
executive Vice President Vice President, Operations Support
& Chief Operating Officer Entergy Operations, Inc.
Entergy Operations, Inc.
P. O. Box 31995 P. O. Box 31995 Jackson, MS 39286-1995
. Jackson, MS 39286-199 Wise, Carter, Child & Caraway Director, Divislors of Radiation.
P.' O. Box 651 Control and Emergency Management Jackson, MS 39205 Arkansas Department of Health 4815 West Markham Street, Slot 30 Little Rock, AR 72205-3867 Winston & Strawn 1400 L Street, N.W.
Washington, DC 20005 3502 Manager, Rockville Nuclear Licensing Framatone Technologies 1700 Rockville Pike, Suite 525 Rockville, MD 20852 Senior Resident inspector U.S. Nuclear Regulatory Commission P. O. Box 310 London, AR 72847 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 i
Arlington, TX 76011 8064 County Judge of Pope County l
Pope County Courthouse Russellville, AR 72801
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9804150415 980410 PDR ADOCK 05000313 P
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l UNITED STATES g
g NUCLEAR REGULATORY COMMISSION o
'2 WASHINGTON, D.C. 20646 0001 d
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4 ENTERGY OPERATIONS INC.
DOCKET NO. 50-313
. ARKANSAS NUCLEAR ONE. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.190 License No. DPR-51 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated February 9,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission'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 Commission; 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 l
Commission's regulations; D.
The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and l
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
6 a
2-2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and Parag aph 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. 190, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION iW illiam Reckley, Project Manager Project Directorate IV-1 Division of Reactor Projects lil/IV i
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: April 10, 1998 l
i
- 4, L.
S.
ATTACHMENT TO LICENSE AMENDMENT NO.190 FACILITY OPERATING LICENSE NO. DPR 51 DOCKET NO. 50-313 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
REMOVE PAGES INSERT PAGES 27 27 110k 110k 1101 1101 110m 110m 110m1 110m1 110n 110n 110o1 11001
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l 3.1.6 Lenkega Spicificttien 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 gym 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 i
through a non-isolable fault in a reactor coolant system 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 150 gallons per day (0.104 ppm), 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 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
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 until the leak is repaired or until 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 sensitive 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 detect leakage and reactor building air samples are taken and analyzed in the laboratory at least once per shifts other-wise, be in at least Not 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 f
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 Amendment No. p,u s,ue,u4,449,190 27
A tuba inspectica (pursunnt to specificatien 4.18.5.o.9) ch:11 b2 perfermed an ecch colcated tuba.
If cny coloctcd tub 2 Caos nst permit tha peacaga of tha eddy current prrbe for o tubs 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)
Group A-2: Unplugged tubes with sleeves installed.
(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.
All tubes which have been repaired using the zeroll process will have the new roll area inspected during the inservice inspection.
The second and third sample inspections during each inservice l!
c.
inspection 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 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 Less than 5% of the total tubes inspected are degraded tubes and none of the inspected tubes are defective.
C-2 One or more tubes, but not more than it of the total tubes inspected, are defective, or between 5% and 10% of the total tubes inspected are degraded tubes.
C-3 Nore than lot of the total tubes inspected are degraded tubes or more than 16 of the inspected tubes are defective.
Amendment No. M,4,M,M6,M4,190 11ok
NOTES:
(1)
In cil inrpsetiens, pr;vicusly d:ge:d:d tubes whoso degradaticas have est be:n cp:nn:d by a closve must exhibit cignificant (>100) furth2r wall penstratiens to be included in the above percentage calculations.
(2)
Where special inspections are performed pursuant to 4.10.3.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 general steam generator inspection.
(3)
Where special inspections are performed pursuant te 4.10.3.b, defective or degraded tube indications found in the new roll area as a result of the inspection and any indications found above the new roll area, are not included in the determination for the inspection results category of a general steam generator inspection..
4.10.4 Insoection Intervals The above-required inservice inspections of steam generator tubes shall be performed at the following frequencies:
a.
The ha line 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 ga:oup* 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 4.10-2 at 40-month intervals 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 pravious inspection. The increase in inspection frequency shall apply until a subsequent inspection meets the conditions specified in 4.10.4.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 subsequent to any of the following conditions:
1.
Primary-to-secondary leakage in excess of the limits of Specification 3.1.6.3.b (Inservice inspection not required if leaks originate from tube-to-tubesheet welds.
If the leaking tube is from either Group A-1 or A-3 as defined in Specification 4.10.3.a.3, all of the tubes in the affected group in this steam ger.erator may be inspected in lieu of
- A group of tubes means: (a) All tubes inspeted pursuant to 4.10.3.a.3, or (b) All tubes in a steam generator less those inspected pursuant to 4.10.3.a.3.
Amendment No. M,46,M,M6,H4,190 1101
ths first camplo in psetian cpseificd in Table 4.10-2.
If th2 Csgradatier. mech:nica which caused tha lock is limited to o cpscific partien of tha tubs icngth, th3 inspsetica par this paragraph may be limited to the affected portion of the 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.
If the leaking tube has been repaired by the reroll process and ia leaking in the new roll area, all of the tubes in the steam generator that have been repaired by the reroll process will have the new roll area inspected. If the results of this inspection fall into the C-3 category, all of the tubes with zerolled areas in the other steam generator will also be similarly inspected.
This inspection will be in lieu of the first sample ii.spection specified in Table 4.10-2.
2.
A seismic occurrence greater than the operating Basis Earthquake, 3.
A loss-of-coolant accident requiring actuation of the engineered safeguards, or 4.
A main steam line or feedwater line break.
4.10.5 Acceptance Criteria a.
As used in this specific ' ion:
1.
Tubing or Tube means that portion of the Li.be or sleeve which forms the primary system to secondary system pressure boundary.
2.
Imoerfection 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.
3.
Degradation means a service-induced cracking, wastage, wear or general corrosion occurring on either the inside or outside of a tube.
4 Degraded Tube means a tube containing imperfections 5 20% of the nominal wall thickness caused by degradation, except where all degradation has been spanned by the installation of a sleeve.
5.
4 Degradation means the percentage of tha tube wall thickness affacted or removed by degradation.
6.
Defect means an imperfection of such severity that it exceeds the plugging limit except where the imperfection has been spanned by the installation of a sleeve. A tube containing a defect in its pressure boundary is defective.
7.
Pluosine Limit means the imperfection depth at or beyond which the tube shall be restored to serviceability by the installation of a sleeve, rerolled, or removed from service l
because it may become unserviceable prior to the next inspections it is equal to 40% of the nominal tube wall thickness.
The reroll repair process will only be used to repair tubes with defects in the upper tubesheet area. The reroll repair process will be performed only once per steam generator tube using a 1 inch roll length. The new roll area must be free of detectable degradation in order for the repair to be considered acceptable.
The zeroll repair process is described in the topical report, RMt-10232F, Revision 00.
Amendment No. H,4,M,M6,4H,190 110m
8.
Unervimeblo describes tha conditica of a tubs 'if it 1caks er centsins o defcet largs canugh to offset its structur:1 int grity in th3 cvent cf cn op3rsting Basic Earthquaks, o 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. For tubes that have been repaired by the zeroll process within the upper tubesheet, that portion of the tube above the new roll can be excluded from future periodic inspection requirements because it is no longer part of the pressure boundary once the repair roll is installed.
b.
The steam generator shall be determined operable after completing s
the corresponding actions (plug, recoll, or sleeve all tubes lj exceeding the plugging limit and all tubes containing through-wall cracks) required by Table 4.10-2.
l 4.18.6 Reports Following each inservice inspection of steam generator tubes, the complete results of the inspection shall be reported to the NRC. This report, to be submitted within 45 days of inspection completion, shall include:
Number and extent of tubes inspected; a.
i b.
Location and percent of wall-thickness penetration for each indication of an imperfections l!j Identification of tubes plugged and tubes sleeved; and l
c.
d.
Number of tubes repaired by zerolling and number of indications I
detected in the new roll area of the repaired tubes.
This report shall be in addition to a special Report (per Specification 6.12.5.d) required for the results of steam generator tube inspections which j
fall into Category C-3 as denoted in Table 4.18-2.
The Cossaission shall be notified of the results of steam generator tube inspections which fall into Category C-3 prior to resumption of plant operation. The written Special Report shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.
Amendment No. gM,M,W6,H4,46, 110ml
- Base, Th3 curveilicace requirements for in:p ctica ef tha ct:am g:nsrstar tub s cacure that the structural integrity of this portion of the RCS will be maintaineds 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 1
degradation due to design, manufacturing errors, or inservice conditions that lead to corrosion. 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.
steam generator tubes that are degraded beyond the repair limit can either be plugged, sleeved, or zerolled. The steam generator tubes that are plugged are removed from service by the installation of plugs at both ends of the associated tube and thus completely removing the tube from service.
Degraded steam generator tubes can also be repaired by the installation of sleeves which span the area of degradation and sorve as a replacement pressure boundary for the degraded portion of the tube, thus permitting the tube to remain in service.
Degraded steam generator tubes can also be repaired by the rerolling of the tube in the upper tubesheet to create a new roll area and pressure boundary for the tube. The zerolling methodology establishes a new pressure boundary below the degradation, thus permitting the tube to remain in service. The degraded tube above the new roll area can be excluded from future periodic inspection requirements because it is no longer part of the pressure boundary once the repair roll is installed in the upper tubesheet. The rerolling repair process will only be used to repair defects in the upper tubesheet in accordance with RAN-10232P, Revision 00.,
All tubes which have been repaired using the reroll process will have the new roll area inspected during future inservice inspections. Defective or degraded tube indications found in the new roll and any indications found in the original roll need not be included in detemnining the Inspection Results Category for the generator inspection.
The zeroll repair process will only be used to repair tubes with defects in the upper tubeshcot area. The zeroll repair process will be performed only once per steam generator tube using a 1 inch roll length. Thus, multiple applications of the zeroll process to any individual tube is not acceptable. The new roll area must be free of detectable degradation in order for the repair to be considered acceptable. After the new roll area is initially deemed acceptable, future degradation in the new roll erea will be analyzed to determine if the tube is defective and needs to be removed from service. The zeroll repair process is described in the topical report, BAN-10232P, Revision 00.
Amendment No. 44,44,44,H 4,4 M,M G, 110n 190
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