ML20209H581
| ML20209H581 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/14/1999 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20209H579 | List: |
| References | |
| NUDOCS 9907210018 | |
| Download: ML20209H581 (6) | |
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i PROPOSED TECHNICAL SPECIFICATION CHANGES 9907210018 990714 PDR ADOCK 05000313 P
3.6.6 If, while the reactor is critical, a reactor building isolation valve is determined to be inoperable in a position other than the closed position, the other reactor building isolation valve (except for check valves) in the line shall be tested to insure operability.
If the inoperable valve is not restored within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the reactor shall be broug.
to the cold shutdown condition within an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or tne operable valve will be closed.
Bases Included in reactor building operability are both the reactor building integrity as defined in Specification 1.7 and the reactor building structural integrity.
Structural integrity limitations as described in the ANO Containment Inspection Program ensure the reactor building will be maintained comparable to the original design standards throughout the facility life span.
Visual and other required examinations of tendons, anchorages and surfaces are performed periodically in accordance with station procedures.
These procedures embody applicable requirements of the 1992 Edition with the 1992 Addenda of Section XI, Subsection IWL of the ASME Boiler and Pressure Vessel Code as set forth in 10 CFR 50.55a (g) (6) (ii) (B). Any degradations exceeding the Containment Inspection Program acceptance criteria during inspection surveillances will be reviewed under an engineering evaluation within 60 days of the completion of *.he inspection to determine what impact the degradation has on overall containment operability, if any.
The reactor coolant system c;nditions of cold shutdown assure that no steam will be formed and hence there will be no pressure buildup in the reactor building if the reactor coolant system ruptures.
The selected shutdown conditions are based on the type of activities that are being carried out and will preclude criticality in any occurrence.
The reactor building is designed for an internal pressure of 59 psig and an external pressure 3.0 psi greater than the internal pressure. The design external pressure of 3.0 psi corresponds to a nargin of 0.3 psi above the differential pressure that could be developed if the building is sealed with an internal temperature of 110'F and the building is subsequently cooled to an internal temperature of lens than 50'F.
When reactor building integrity is established, the limits of 10 CFR 100 will not be exceeded should the maximum hypothetical accident occur.
REFERENCE FSAR, Section 5.
l Amendment No. 67, 55 1
6.12.4 Reactor Building Inspection Report j
'6.12.4.1 Any degradation exceeding the acceptance criteria of the containment structure detected during the tests required by the ANO Containment Inspection Prograra shall undergo an engineering evaluation within 60 days of the completion of the inspection surveillance. The results of the engineering evaluation shall be reported to the NRC within an additional 30 days of the time the evaluation is completed. The report shall include the cause of the condition that does not meet the acceptance criteria, the applicability of the conditions to the other unit, the acceptability of the concrete containment without repair of the item, whether or not repair or replacement is required and, if required, the extent, method, and completion date of necessary repairs, and the extent, nature, and frequency of additional examinations.
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Amendment No. 9, M, 94, 444 146
MARKUP OF CURRENT ANO-1 TECHNICAL SPECIFICATIONS (FOR INFO ONLY)
3.6.6 If, while the reactor is critical. a reactor building isolation valve is determined to be inopers te in a position other than the closed position, the other react.c building isolation valve (except for check valves) in the line shall be tested to insure operability.
If the inoperable valve is not restored within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the reactor shall be brought to the cold shutdown condition within an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or the operable valve will be closed.
Bases Included in reactor buildina operability are both the reactor buildino intearity as defined __In_Speciflcation 1.7 and the reactor building structural intg g_i h S_tructural intearityJimitations as describ_ed in the ANO Containment Inspection Pr_ogram ensure the reactor buildina will be maintained comparable to the
(
original design stand.ards_throughout the facility life span.
Visual and other i
geguired examinations of tendons, anchoraces and_ surfaces are performed getiodically in accordance with station procedures. These procedures embody j
ggo,licable re_quirements of the 1992 Edition with the 1992 Addenda of Section__XI 1 Subsection IWL of the ASME Boiler and Pressure Vessel Code as set forth in 1
10 CFR 50. 55a (a) (6) (ii) (B). Any dearadations exceeding _thg_qpntainment j
Inspection Program acceptance criteria durino inspection surveillances will be i
reviewed under an enaineerina evaluation within 60 days of the comgletion of the inspection to_ determine what impact the degradation has on overall contairment
{
operabilityg if any1
)
q The reactor coolant system conditions of cold shutdown assure that no steam I
will be formed and hence there will be no pressure buildup in the reactor building if the reactor coolant system ruptures.
The selected shutdown conditions are based on the type of activities that are being carried out and will preclude criticality in any occurrence.
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The reactor building is designed for an internal pressure of 59 psig and an external pressure 3.0 psi greater than the internal pressure.
The design external pressure of 3.0 psi corresponds to a margin of 0.5 psi above the differential pressure that could be developed if the building is sealed with an internal temperature of 110*F and the building is subsequently cooled to an internal temperature of less than 50*F.
When reactor building integrity is established, the limits of 10 CFR 100 will not be exceeded should the maximum hypothetical accident occur.
REFERENCE FSAR, Section 5.
1 Amendment No. 64, 55
%'./
6.12.1 Ocleted Reactor Building Inspection Report l
6.,J 2. 4.1 Any de.grAdat;1on exceeding the accep_tance criteria of the containment structure detected during_t_he_ tests _ required by_the ANO Containment Inspection _Progr.am shall_ unde _rgo an engine _ering evaluation within_6_0__ days of the comyletion of the inspect _ior]
surveillance. The results_of the engineering evaluation shall be report;e_d to th< NRC withirtagadditional 30 days of the time _the eval _uation is completed _.
The_ report shall include the cause of the condition that does not meet the acceptangpe_ criteria, the gpplicability of the conditions to the other unit,_ thy jleceptabil_itJ_of the concrete containment wi':hout reppai_r_ofdh3 item whether or not repair or replacement is required _and,_if a
required, the exten1, method,_and completion date of necessary repai.rs,_and the extent, nature,__and f re_que_ngy of addij;;ional examinations.
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Amendment No. 9, 43, 94, 444 146
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