ML19318B891
| ML19318B891 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 06/24/1980 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML19318B885 | List: |
| References | |
| NUDOCS 8006300257 | |
| Download: ML19318B891 (4) | |
Text
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3/4.4.10 STRUCTURAL INTEGRITY ASME CODE CLASS 1, 2 A.ND 3 COMPONENTS LIMITING CONDITION FOR OPERATION 3.4.10.
The structural integrity of ASME Code Class 1, 2 and 3 components shall be mair.tained in accordance with Specification 4.4.10.
APPLICABILITY: ALL MODES ACTION:
With the structural integrity of any ASME Ccde Class 1 component (s) a.
not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolant System temperature more than 50 F above the minimum temperature required by NDT considerations. However, plant heatup is permitted with hanger RCH-118 inoperable prior to initial criticality.
I b.
With the structural integrity of any ASME Code Class 2 component (s) not conforming to the above requirements, restore the structural 3
integrity of the affected component (s) to within its limit or isolate
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the affected component (s) prior to increasing the Reactor Coolant System temperature above 200 F.
With the structural integrity of any ASME Code Class 3 component (s) c.
not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) from service.
d.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REOUIREMENTS 4.4.10.
In addition to the requirements of Specification 4.0.5, each Reactor Coolant Pump flywheel shall be inspected per the recommendations of Regulatory Position C 4.b of Regulatory Guide 1.14, Revision 1, August 1975.
l 8006300 2T7 SEQUOYAH - UNIT 1 3/4 4-27
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ENCLOSURE 2 REASONS AND JUSTIFICATIONS FOR PROPOSED CHANGES TO SEQUOYAll NUCLEAR PLANT UNIT 1 TECliNICAL SPECIFICATIONS
1.
Specification 3.4.10, Page 3/4 4-27 TVA is in the process of verifying the adequacy of the as-built piping supports and restraints relative to the requirements of OIE Bulletin,
79-14 and the letter from J. P. O'Reilly to H. G. Parris dated April 29, 1980. Aa specified in the letter, all required actions will be resolved before initial criticality.
The proposed change will allow plant heatup to take place with hanger RCH-118 inoperable. Hanger RCH-118 is located on the pressurizer relief line. As stated above, the deficiency will
'be resolved before initial criticality.
Therefore, the requested change is only applicable during the period before initial criticality. At that time, the technical specification will be restored to its original form.
Before initial criticality, no fission product inventory exists. The decay heat load is negligible.
Therefore, plant heatup with RCH-ll8 inoperable poses no additional risk to the health and safety of the public.
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