ML20115B927
| ML20115B927 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 10/08/1992 |
| From: | Larkins J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20115B929 | List: |
| References | |
| NPF-06-A-139 NUDOCS 9210190017 | |
| Download: ML20115B927 (9) | |
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UNITED STATES S-wJ E
NUCLEAR REGULATORY COMMISSION fi d T [g' -
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DOCKET NO. 50-368' 8RKANSAS' NUCLEAR ONE. UNIT NO. 2 AMEN 0 MENT TO FALIllTY OPERATING LICENSE Amendment-No. 139 License No.-NPF-6 1.
The Nuclear Regulatory Commission (the-Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the.
licensee), dated July 9,71992,- a:; supplemented by htters dated September 11,. and October 7,1992,- complie:: with in standards and requirements of the: Atomic Energy Act of 1954, as amended-(the Act)',
and the Cominission'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.
conductee.n-compliance with the-Commission's regulations;,
D.
The issuance of thistlicense amendment will 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-Commission's regulations and all applicable requirements have been-satisfied.
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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. NPF-6 is hereby amended to read as follows:
2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.139, 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 John T. Larkins, Director Project Directorate IV-1 Division of Reactor Projects - Ill/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
October 8, 1992
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6.TTACHMENT TO LICENSE AMENDMENT NO.139 FACIllTY 0PERATING LICENSE NO. NPF-Q QOCKET NO. 50-368 Revise 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.
The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE PAGES INSERT PAGES 3/4 2-3 3/4 2-3 3/4 6-7 3/4 6-/
B 3/4 6-2 B 3/4 6-2
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l ARKANSAS - UNIT 2 3/4 6-7 Amendment No. 7, 24, 139
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POWER DISTRIBUTION LIMITS RADIAL PEAKING FACTORS LIMITING CONDITION FOR OPERATION 3.2.2 The measured PLANAR RADIAL PEAKING FACTORS (F y) shall be less than or C
equal to the PLANAR RADIAL PEAKING FACTORS (F Limit Supervisory Systen (COLSS) and in the C5Ee) used in the Core Operating Protection Calculators (CPC).
APPLICABILITY:
MODE 1 above 20% of RATED THERMAL POWER.*
ACTION:
With a F*
exceeding a corresponding F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> either:
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y gy Adjust the CPC addressable constants to increase the multiplier a.
applied to PLANAR RADIAL PEAKING FACTOR by a factor equivalent to
>F* /F and restrict subsequent operation so that a margin to the COLS$ operating limits of at least ((F /Fc ) - 1.03 x 100%
is maintained; or
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Adjust the affected PLANAR RADIAL PEAKING FACTORS (F, ) used in
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the COLSS and CPC to a value greater than or equal to the measured PLANAR RADIAL PEAKING FACTORS (F" ); or l
y c.
Be in at least HOT STANDBY.
SURVEILLANCE REQUIREMENTS 4 ~. 2.1 The provisions of Specification 4.0.4 are not applicable.
4.2.2.2 The measured PLANAR RADIAL PEAKING FACTORS (F* ), obtained by l
y using the incore detection system, shall be determined to be less than l or equal to the PLANAR RADIAL PEAKING FALTORS (Fc ) used in the COLSS l
and CPC at the following intervals:
y Af ter each fuel loading with THERMAL POWER greater than 40%
a.
but prior to operation above 70% of RATED THERMAL POWER, and b.
At least once per 31 days of accumulated operation in MODE 1.
- See Special Test Exception 3.10.2.
ARKANSAS - UNIT 2 3/4 2-4 Amendment No. 24
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5 ATTACHMENT TO LICENSE AMENDMENT NO.139 FACILITY OPERATING LICENSE NO. NPF-6 DOCKET NO. 50-3E8 Revise 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.
The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE PAGES INSERT PAGES 3/4 2-3 3/4 2-3 3/4 6-7 3/4 6-7 8 3/4 6-2 B 3/4 6-2 i
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"'^4"#"idsgpEAIR ge ARKANSAS UNIT 2 3/4 6-7 mendment No. 7 /A, 139 s
CONTAINMENT SYSTEMS _
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CONTAINMENT STRUCTURAL DREGRITY
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l.IMITING CONDITION FOR OrERATION 3.6.1.5 The stnJctural integrity of the containment shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.1.5.
APPLICABILITY : MODES 1, 2, 3 and 4 ACTION:
With the structural integrity of the contaiNnent not Confoming to tne above requirements, restore the structural integrity to within the limits within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT STANDBY within the next 6 nours 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 />.
SURVEILLANCE REOUIREMENTS i
4. 6.1. 5.1 Containment Tencons The containment tendons ' structural integrity snaii ne oemonstratec at the end of one, three and #ive years il #ollowing tne initial containment structural integrity test and at five The tendons' structural integrity snall be l year intervals thereafter.
demonstrated by a visual examination (to the extent practical and witn-out dismantling load bearing components of the anchorage) of a repre-sentative sample
- of at least 21 tendons (6 dome 5 vertical, and 10 neop) and verifying no abnormal degradation. Unless there is evidence of abnormal degradation of tne :entiinment tendons during the first three tests of the tencons, the number of tendons examined during sub-setuent tests inay be reduced to a representative sample of at least 9 tencons (3 dome, 3 vertical and 3 hoop).
"For each inspection, the tendons shall be selected on a random but representative basis so that the sample group will change somewhat for each inspection; however, to develop a history of tendon perfomance and to correlate the observed data, one tendon from each group (dome, vertical, and noop) may be kept unchanged after the initial selection.
ARKANSAS-UNIT 2 3/4 6-8
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3/4.6 CONTA!NMENT SYSTEMS BASES 3/ 4. 6.1 PRIMARY CONTAINMENT 3/ 4. 6.1.1 CONTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY ensures that the release of radio-active materials from the containment atmosphere will be restricted to those leakage paths and associated ler.k rates assumed in the accident analyses. This restriction, in conjunction with the leakage rate limi-tation, will limit the site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions.
3/4.6.1.2 CONTAINMENT LEAKACE The ' limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the accident analyses at the peak accident pressure, P. As an added con-a servatism, the measured overall integrated leakage rate is further t fof p(ossible degradation of the contain-as appli limited to <-0.75 L or 0
the periodic tests ko ac<oun.75 L c
ment leakage barriers between leakage tests.
The surveillance testing for measuring leakage rates are consistent with the requirements of Appendix "J" of 10 CFR 50.
3/4.6.1.3 CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and containment leak-rate.
Surveillance testing of the air lock seals provides assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.
ARKANSAS - UNIT 2 B 3/4 6-1
CONTAINMENT SYSTEMS BASES 3/4.6.1.4 INTERNAL PRESSURE. AIR TEMPERATU}f AND REIATIVE HUMIDITY The limitations on containment internal pressure, average air temperature and relative humidity ensure that 1) the containment structure is prevented from exceeding its design negative pressure differential with respect to the outside atmosphere of 5.0 psig, 2) the containment peak pressure does not exceed the design pressure of 54 psig during design basis conditions, and 3) the ECCS analysis assumptions are maintained.
The limitation on containment average air temperature ensures that the containment liner plate temperature does not exceed the design temperature of 300'F during LOCA conditions. The containment temperature limit is consistent with the accident analyses. Figure 3.6-1 represents l
analysis limits and does not account for instrument error.
3/4.6.1.5 CONIAINMENT STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containrent will be maintained comparable to the original design standards for the life of the facility. Structural integrity is required to ensure that the containment will withstand the maximum pressure of 53.4 psig in the event of a LOCA.
The visual examination of tendons, anchorages and containment surfaces and the Type A leakage tests of the Unit 2 containment in conjunction with the required surveillance activities of the Unit I containment are sufficient to demonstrate this capability.
The surveillance requirements for demonstrating the containment's structural integrity are in compliance with the recommendations of Regulatory Guide 1.35 " Inservice Surveillance of Ungrouted Tendons in Prestressed Concrete Containment Structures", January 1976.
3/4.6.1.6 CONTAINMENT VENTILATION SYSTEM The containment purge supply and exhaust isolation valves are required to be closed during plant operation since these valves have not been demonstrated capable of closing during a LOCA. Maintaining these valves closed during plant operations ensures that excessive quantities of radioactive materials will not be released via the containment purge system.
ARKANSAS - UNIT 2 B 3/4 6-2 Amendment No. 139