ML20247E123

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Proposed Tech Spec 3/4.4.8, Structural Integrity
ML20247E123
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 05/10/1989
From:
DETROIT EDISON CO.
To:
Shared Package
ML20247E120 List:
References
NUDOCS 8905260131
Download: ML20247E123 (3)


Text

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< REACTOR COOLANT SYSTEM 3/4.4.8 STRUCTURAL INTEGRITY \

LIMITING CONDITION FOR OPERATION 3.4.8 The structural integrity of ASME Code Class 1, 2, and 3 components shall be maintained in accordance with Specification 4.4.8.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3, 4, and 5.

ACTION:

a. With the structural integrity of any ASME Code Class 1 corponent(s) not conforming to the above requirements, restore the strJCtural 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.

b. With the structural integrity of any ASME Code Class 2 component (s)

- 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 above 200'F.

( c. With the structural integrity of any ASME Code Clars 3 component (s) 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) free service.

s d. The provisions of Specification 3.0.4 are not applicable.

, w SURVEILLANCE REQUIREMENTS 4.4.8 No requirements other than Specification 4.0.5,and th guid:1ka af-WREG-03H,-Technical-Repei t. un riaterial-Selection-end-Processing-Guidelines for """ C;01 ant-fressure-Boundary "f pbg,-Revis4e-1.

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( 3/4 4-25 FERMI - UNIT 2

APPLICABILITY SURVEILLANCE REQUIRED ef7S (Continued)

c. The provisions of Specification 4.0.2 are applicable to the above required frequencies for perforsing inservice inspection and testing activities,
d. Performance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements.
e. Nothing in the ASME Boi1Ler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical l Specification. l
f. The Inservice Inspection (NDE) Program for piping identified in NRC Generic Letter 88-01, dated January 25, 1988, "NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping",

shall be performed in accordance with the staff positions on schedule, methods and personnel, and sasple expansion included in this generic letter.

FERMI - UNIT 2 3/4 0-3

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APPLICABILITY BASES 4.0.5 This specification ensures that inservice inspection of j ASME Code Class 1, 2 and 3 components and inservice testing of ASME j Code Class 1, 2 and 3 pumps and valves will be performed in accordance with a periodically updated version of Section II of the ASME Boiler and Pressure Vessel Code and Addenda as required by 10CFR50, Section 50.55a. Relief from any of the above requirements has been provided in writing by the Commission and is not a part of these Technical Specifications.

This specification includes a clarification of the frequencies of performing the inservice inspection and testing activities required by Section II of the ASME Boiler and Pressure Code and applicable Addenda. This clarification is provided to ensure consistency in surveillance intervals throughout these Technical Specifications and to remove any ambiguities relative to the frequencies for performing the required inservice inspection and testing activities.

Under the terms of this specification, the more restrictive requirements of the Technical Specifications take precedence over the ASME Boiler and Pressure Vessel Code and applicable Addenda. For example, the requirements of Specification 4.0 4 to perfors surveillance activitics prior to entry into an OPERATIONAL CONDITION or other specified applicability condition takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows pumps to ,

be tested up to one week after return to normal operation. And for example, the Technical Specification definition of OPERABLE does not grant a grace period befern a device that is not capable of performing

. its specified function is declared inoperable and takes precedence over the ASME Boiler and Pressure Vessel provision which allows a valve to be incapable of performing its specified function for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before being declared inoperable.

NRC Generic Letter 88-01 identified NRC's position on intergranular stress corrosion cracking (IGSCC) in BWR Stainless Stee'l weldsents. This letter establishes requirements to inspect these weldsents to a speciel schedule and by procedures, personnel and 2 equipment that are qualified under a formal program approved by the 2 NRC.

FERMI - UNIT 2 B 3/4 0-3 l

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