ML20217C493

Proposed Improved Tech Specs 5.6.2.8.c Re Reactor Coolant Pump Motor Flywheel Insp

ML20217C493
Person / Time
Site:	Crystal River
Issue date:	03/20/1998
From:	FLORIDA POWER CORP.
To:
Shared Package
ML20217C469	List: 3F0398-07, Rev 0 to LAR 227 to License DPR-72,requesting Editorial Change to Improved Tech Specs 5.6.2.8.c Re Reactor Coolant Pump Motor Flywheel Insp ML20217C493
References
NUDOCS 9803270042
Download: ML20217C493 (4)

Text

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4 ATTACHMENT B LICENSE AMENDMENT REQUEST #227, REVISION 0 REACTOR COOLANT PUMP MOTOR FLYWHEEL INSPECTION Proposed Technical Specifications Change Strikeout / Shadowed Page Deletions are indicated by strikeout Addition of text is indicated by highlighting 9803270042 900320 PDR ADOCK 05000302  !

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Procedures, Programs and Manuals 5.6

, 5.6 Procedures, Programs and Manuals 5.6.2.6 Post Accident Sampling (continued)

c. Provisions for maintenance of sampling and analysis equipment.

5.6.2.7 Containment Tendon Surveillance Program This program provides controis for monitoring any tendon degradation in concrete containments, including effectiveness of its corrosion protection medium, to ensure containment structural integrity. The program shall include baseline measurements prior to initial operations. The Containment Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be in accordance with Regulatory Guide 1.35, Revision 3, 1990.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Containment Tendon Surveillance Program inspection frequencies.

5.6.2.8 Inservice Inspection Program This program provides controls for inservice inspection of ASME Code Class 1, 2, and 3 components, including applicable supports.

The program shall include the following:

a. Provisions that inservice inspection of ASME Code Class 1, 2, and 3 components shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50.55a;

b. The provisions of SR 3.0.2 are applicable to the frequencies for performing inservice inspection activities;

c. Inspection of each reactor coolant pump flywheel per the recommendation of Regulat4eniiFyl Position eC.4.b of Regulatory Guide 1.14 RevisTBn 1, August 1975, except, the l vcl=teric si6fEiffil, examinations and complete surface examination'"6f*thi' flywheels for the Second ISI Interval may be delayed o.ne cycle to coincide with the Sprir.g 1003 BrefuelingDeutageR;and

d. Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any TS.

(continued) Crystal River Unit 3 5.0-11 Amendment No. 4 9

ATTACHMENT C LICENSE AMENDMENT REQUEST #227, REVISION 0 REACTOR COOLANT PUMP MOTOR FLYWHEEL INSPECTION Proposed Technical Specification Page Revision Bars

Procedures, Progra:s and Manuals 5.6 S.6. Procedures, Programs and Manuals 5.6.2.6 Post Accident Sampling (continued)

c. Provisions for maintenance of sampling and analysis equipment.

5.6.2.7 Containment Tendon Surveillance Program This program provides controls for monitoring any tendon degradation in concrete containments, including effectiveness of its corrosion protection medium, to ensure containment structural integrity. The program shall include baseline measurements prior to initial operations. The Containment Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be in accordance with Regulatory Guide 1.35, Revision 3, 1990. The provisions of SR 3.0.2 and SR 3.0 ' are applicable to the Containment Tendon Surveillance Prc7 inspection frequencies. 5.6.2.8 Inservice Inspection Program This program provides controls for inservice inspection of ASME Code Class 1, 2, and 3 components, including applicable supports. The program shall include the following:

a. Provisions that inservice inspection of ASME Code Class 1, 2, and 3 components shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50.55a;

b. The provisions of SR 3.0.2 are applicable to the frequi:.cies for performing inservice inspection activities;

c. Inspection of each reactor coolant pump flywheel per the recommendation of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August 1975, except, the volumetric examinations and complete surface examination of the flywheels for the Second ISI Interval may be delayed one cycle to coincide with Refueling Outage 11R; and l

d. Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any TS.

(continued) Crystal River Unit 3 5.0-11 Amendment No. e}}