ML19319D499

Forwards SER & List of Outstanding Issues to Be Resolved Prior to Issuance of Ol.W/O SER

ML19319D499
Person / Time
Site:	Crystal River
Issue date:	07/05/1974
From:	Schwencer A US ATOMIC ENERGY COMMISSION (AEC)
To:	Rodgers J FLORIDA POWER CORP.
References
NUDOCS 8003170627
Download: ML19319D499 (3)

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!R BIRION M '[' ~ ~i s

local PDR Docket File LhR 2-3 Reading i

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Docket No.50-34G A Schwencer B. C. Bucklev E I goulbourn' e (2)

V. A. Moore ACRS (16)

Florida Power Corporation 5 extra cys

.ATIN: Mr. J. T. Rodgers C. Miles "f.fip..p'

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'Assistat Vice President rgEdDy;

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Pive copies of the Safety Evaluation prepared by the Directorate of e i...;(.

Licensing relating to your Crystal River Unit 3 Nuclear Plant are

' 7;1 enclosed for your infomation.

A = =her of issues, identified during the review, remain outstanding.

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'lhese issues are briefly described in Enclosure 1.

References to pertinent sections in the SER are also provided for further information.

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1. Schwencer A. Schwencer, Chief Light Water. Reactors Branch 2-3 I

Directorate of Licensing

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2. ~ Safety Byaluation Report

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'Mr. Dave Hopkins O,i JVice^ President ( Geneml Counsel lhviv _..t.a1 Protection Agency

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-1421 Peachtree Street, N.B.

.c Stt-Petersburg, Florida 33733 TAtlanta, Georgia 30309 h.,

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Citrus County

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' OUTSTANDING ISSUES SAFETY EVALUATION REFORT CRYSTAL RIVE 2, IJUIT 3 Issues for which our review is not co=pleted and for which cogpletion will be required prior to issuance of an operating license.

1.

Verification of atmospheric diffusion esti=ates and meteorological data collection system confor=ance with Regulatory Guide 1.23 (Sections 2.3.3, 2.3.6).

2.

Compliance with t,he new ECCS criteria (Section 6.3.5).

i 3.

Provision for redundant and independent indication systems for each core flooding tank isolation valve (Section 7.3.1).

l-4.

Steam line break isolation system (Section 7.3.2).

j 5.

Auxiliary feedwater systes instrumentation conformance with i

IEEE Std 279-1963 (Section 7.4).

4 6.

Instrumentation required to follow course of an accident (Section 7.5).

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nacidual haat rcnoval (RnR) oysten valve interlock provisions with I

l regard to diverse principles to prevent opening and for autocatic closure of RER valves (Section 7.6).

1 8.

Conformance with criteria of minimum separation between redundant safety-related cables (Section 7.9.1).

9.

Potential' flooding of switchgear room as a result of failure of firewater piping (Section 7.9.2).

10. Verification that battery roon ventilation systen will preclude accu =ulation of explosive hydrogen mixtures (Section 7.9.3).

11.

Conformance of 230 Kv switchyard breakers control power separation with GDC 17 (Section 7.9.4).

12.

Justification for use of manual switches for disconnecting power to each group of control rods (Section 7.10).

13.

Confor=ance of feeder breaker connecting 4160/480 V transformer with emergency buses with Class IE requirements (Section S.3).

-14.

Verification that diesel generators similar to those used in this plant have been qualified for use in other nuclear facilities (Section 8.3).

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Modification of 480 V tie breakers to assure independence of redundant energency buses (Section 8.3).

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Conformance of redundant d-c systens with GDC 17 and IEEE Std 308-1969 (Section 8.4).

l'.. Modifications to alternate power sources to assure independence of two of the redundant 120 V vital a-c buses (Section 8.4).

18. Verification that the auxiliary feedwater system meets the single failure criteria coincident with failure of a high energy line break (Sections 7.4, 9.2.4 and 10.4.4).

19. Review and evaluation of operator requalification program for conformance with Appendix A of 10 CFR Part 55 (Section 13.1).

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