ML20217P518

Proposed Tech Specs Re Reactor Coolant Pump Motor Flywheel Insp

ML20217P518
Person / Time
Site:	Crystal River
Issue date:	04/28/1998
From:	FLORIDA POWER CORP.
To:
Shared Package
ML20217P511	List: 3F0498-06, LAR 232,Rev 0 to License DPR-72,changing Scope & Frequency of Volumetric & Surface Insps for CR-3 Reactor Coolant Pump Motor Flywheels ML20217P518
References
NUDOCS 9805060337
Download: ML20217P518 (4)

Text

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1 FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50-302/ LICENSE NUMBER DPR-72 ATTACHMENT C

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LICENSE AMENDMENT REQUEST #232 REVISION O Proposed Technical Specification Change Page Strikeout / Shaded e885I80$[oSooS$oa p PDR

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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 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 freguencies, 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.

l 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, i 2, and 3 components shall be performed in accordance with j 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. Inseryicelinspection of each reactor coolant pump flywheel gcr it,^ r^dc :cndction of Rc-"latica ."csition c.0.b .f m-u mc~L._letcry-_4, -

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allfbe} performed at?leastTonce ever sb . inservice, inspection shall:be e either;y! ten year,s.> sThe aneultrasonic" examinationpofethe; volume:from therinner: bare off the flywheelf talthe circleKoffone-half;:theiouterf surface examination 4fortexposed-surfacestof1the radius::oSa disassembl . s.d flywheels; . The recommendations'delineatedLin' Regulatory Guide;1.14fPositionsL3,f4and15':of;SectionC.4.bishall' applyj

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. 163 l

l

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FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 DOCKET NUMBFsR 50-302/ LICENSE NUMBER DPR-72 ATTACHMENT D LICENSE AMENDMENT REQUEST #232 REVISION O Proposed Technical Specification Change Page Revision Bars l

l 1

.'. 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 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 orior to initial operations. -The Containment Tendon Surveillance Program, inspection freguencies, 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.

Theprogramshallincludethefollowing:

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 applichble 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. Inservice inspection of each reactor coolant pump flywheel shall be performed at least once every ten years. The inservice inspection shall be either an ultrasonic examination of the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination for exposed surfaces of the disassembled flywheel s. The recommendations delineated in Regulatory Guide 1.14, Positions 3, 4 and 5 of Section C.4.b shall apply.

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

(continued)

Crystal River Unit 3 5.0-11 Amendment No.