ML19270G537

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Delineates Criterion to Develop plant-specific Info Packages on Site Visits
ML19270G537
Person / Time
Site: Beaver Valley, Surry, Maine Yankee, FitzPatrick  Dominion icon.png
Issue date: 04/11/1979
From: Russell W
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 7906130026
Download: ML19270G537 (2)


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UNITED STATES j#

w NUCLEAR REGULATORY COMMISSION

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j WASHINGTON. D. C. 20666 e

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NOTE T0:

Review Team Members FROM:

William T. Russell RE:

SITE VISITS OBJECTIVE:

DEVELOP PLANT SPECIFIC INFORMATION PACKAGES I.

General - For Safe Shut-Down and Reg. Guide 1.29 Piping Systems

1) Obtain P & ids (Isometrics if available)
2) Obtain FSAR system discriptions
3) Determine Quality Class I, II, III and boundries.

(should be in 50.55 a(g) submittal - ISI/IST)

4) Determine redundancy (single failure)

(i.e. - single drop lines in RHR, SI etc)

5) Determine interfaces between Safety and Non-Safety Systems, if any (i.e. - aux-feed / main feed) 6)

Detemine if procedures for shutdown w/ minimum safety systems exist II. Determine Affected Systems (i.e. - Those which used SHOCK II)

1) Safety Systems
2) Non-Safety Systems which interface with Safety Systems III. Determine How Remaining Safety Systems were Analyzed
1) NSSS
2) SHOCK I 23,25 357
3) Hand Calculations

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William T. Russell Coordinator 79061800426

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e-DISTRIBUTION H. R. Denton E. G. Case B. Grimes A. Schwencer R. Reid T. Ippolito V. Noonan D. Wigginton S. Hosford R. LaGrange P. Polk C. Nelson D. Neighbors K. Wichman K. Herring Dock t Files S

.60-334 50-280 50-281 50-333 50-309 F. Miraglia W. Paulson 2325 ;58 J. Fair J. Gianelli P. Riehm

s Florida 6 June 1979 Power 3-o-3-a-1 c o a. o " ' ""

CS-79-172 Mr. J. P. O'Reilly, Director Docket No. 50-302 U.S. Nuclear Regulatory Commission Licensee No. DPR-72 Office of Inspection & Enforcement LER No. 79-049/03L-0 101 Marietta St.,

Suite 3100 Crystal River Unit //3 Atlanta, GA 30303 Occurrence Date:

9 May 1979

Dear Mr. O'Reilly:

Enclosed please find Licensee Event Report 79-049/03L-0 and the attached supplementary information sheet, which are submitted in accordance with Technical Specification 6.9.1.9.b.

Should there be any questions, please contact us.

Very truly yours, FLORIDA POWER CORPORATION

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W. P. Stewart Manager, Nuclear Operations JC/rc M

2325 ;59 Nuclear riant Manager 790613001'

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