ML20039E405

Application for Amend to License DPR-72,consisting of Tech Spec Change Request 38,Revision 1 to Add 120 Snubbers to Table 3.7-3.Table Designates Reactor Bldg Snubbers That Are Inaccessible During Operation

ML20039E405
Person / Time
Site:	Crystal River
Issue date:	12/28/1981
From:	Mardis D FLORIDA POWER CORP.
To:
Shared Package
ML20039E396	List: ML20039E395 ML20039E405 ML20039E407
References
TAC-47351, TAC-47352, TAC-47353, NUDOCS 8201070245
Download: ML20039E405 (1)

Text

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TECHNICAL SPECIFICATION CHANGE REQUEST NO. 38 REVISION 1 PROPOSED CHANGr.

Original Submittal:

This change request proposed to revise Table 3.7-3 of the Crystal River Unit 3 Technical Specifications, Appendix A, by adding 118 snubbers and listing their actual build-ing locations.

Revision 1:

This change request proposes to include two (2) additional snubbers to Table 3.7-3 of the Crystal River Unit 3 Technical Specifications, Appendix A,

and to identify snubbers located within the Reactor Building as inaccessible during opera-tion.

REASON FOR PROPOSED CHANGE These 120 snubbers are being added as a result of the review of snubbers used in safety related systems as stated in Florida Power Corporation's letter to the NRC dated November 10, 1978 (Mr.

W.

P.

Stewart to Mr. C. C. Nelson).

The Crystal River Unit 3 Technical Specifications allow the assignment of safety related snubbers to two groups (accessible or inaccessible during plant operation) for inspection interval determination.

The snubbers located within the Reactor Building are being classified as inaccessible during plant operation because Operating Procedures limit Reactor Building access to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per month for personnel safety and -

ALARA considerations.

SAFETY EVALUATION Plant safety will not be compromised by the proposed changes.

The addition of 120 snubbers to Table 3.7-3 increases assurance of system operability by requiring the additional snubbers to be included in the snubber surveillance program.

The classification of snubbers inside the Reactor Building as inacces-sible does not alter operability or surveillance requirements for these snubbers.

The classification only allows them to be considered as an independent set when determining the surveillance interval and number to be functionally tested. No unreviewed safety questions are involved.

Ford (TSCRN38)DN115-2 8201070245 811228 PDR ADOCK 05000302 P

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