ML20198H172

Forwards RAI on Change to T Cold Reduction & RCS Flow Measurement TS to Allow Operation with Reduce Cold Leg Temp & Change Reactor Coolant Sys Flow Measurement from Mass to Volumetric Indication

ML20198H172
Person / Time
Site:	San Onofre
Issue date:	12/18/1998
From:	Clifford J NRC (Affiliation Not Assigned)
To:	Ray H SOUTHERN CALIFORNIA EDISON CO.
References
TAC-MA2238, TAC-MA2239, NUDOCS 9812290255
Download: ML20198H172 (3)

Text

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e L December: 18,1998

~

Mri Harold B. Ray

~ Executive Vice President

' Southern California Edison Company

_ San Onofre Nuclear Generating Station P. O. Box 128 San Clemente, California 92674-0128 l -

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION ON CHANGE TO Tcow

!' REDUCTION AND RCS FLOW MEASUREMENT TECHNICAL SPECIFICATION (TAC _ NOS. MA2238 AND MA2239)

Dear Mr. Ray:

1

.in a letter dated June 16,1998,' Southern California Edison (SCE) submitted a request for amendment to the San Onofre Nuclear Generating Station (SONGS) Units 2 and 3 technical specifications to (1) allow operation with a reduce cold leg temperature, and (2) change reactor coolant system (RCS) flow measurement from mass to volumetric indication.

l- You responded to a request for additional information related to the reactor systems portion of I j

the review by letter dated December 4,1998. To complete our review, we request that you provide the additionalinformation related to the mechanical engineering portion of the review  ;

that is identified in the enclosure within 30 days of the date of this letter. Your timely response .

L to the request for additional information will assist us in meeting your requested schedule. This l Information and the schedule have been discussed with Mr. Jack Rainsberry of your staff.

l

[. Please call me at 301-415-1352 if you have any questions. I l

Sincerely, l

Original Signed by Mel Fields for l

James W. Clifford, Senior Project Manager Project Directorate IV-2

Division of Reactor Projects Ill/IV Office of Nuclear Reactor Regulation Docket Nos. 50-361 DISTRIBUTION

,

and 50-362 Docket File CWu PUBLIC ACRS

Enclosure:

Request for AdditionalInformation PDIV-2 R/F PGwynn, Region IV l EAdensam GPick, Region IV WBateman cc w/ encl: See next page JClifford EPeyton l OGC DOCUMENT NAME: G:\SOA2238A.RAI l- To receive a copy of this document. Indicate in the box: "C" = Copy without enclosures "E" = Copy with enclosures "N" = No copy l OFFICE PDIV_-2/PM _ PDIV-2/LA gg EPeyton.no4:D \

lNAME JClifW.fw ' '

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Mr. Harold B. Ray -2 December 18, 1998 cc w/ encl: j Mr. R. W. Krieger, Vice President Resident inspector / San Onofre NPS l Southern California Edison Company c/o U.S. Nuclear Regulatory Commission i San Onofre Nuclear Generating Station Post Office Box 4329 P. O. Box 128 San Clemente, California 92674 San Clemente, California 92674-0128 Mayor Cha;. man, Board of Supervisors City of San Clemente County of San Diego 100 Avenida Presidio 1600 Pacific Highway, Room 335 San Clemente, California 92672 San Diego, California 92101 Mr. Dwight E. Nunn, Vice President Alan R. Watts, Esq. Southern Califomia Edison Company Woodruff, Spradlin & Smart San Onofre Nuclear Generating Station 701 S. Parker St. No. 7000 P.O. Box 128 Orange, California 92668-4702 San Clemente, California 92674-0128 Mr. Sherwin Harris Resource Project Manager Public Utilities Department City of Riverside 3900 Main Street Riverside, California 92522 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Harris Tower & Pavilion 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011-8064 Mr. Michael Olson San Onofre Liaison San Diego Gas & Electric Company l P.O. Box 1831 l San Diego, California 92112-4150 Mr, Steve Hsu Radiologic Health Branch State Department of Health Services Post Office Box 942732 l Sacramento, Califomia 94234 l

l 4

l REQUEST FOR ADDITIONAL INFORMATION l

PROPOSED RCS COLD LEG TEMPERATURE REDUCTION AND ELIMINATION OF RCS UPPER FLOW LIMIT SAN ONOFRE NUCLEAR GENERATING STATION. UNITS 2 AND 3 DOCKET NOS. 50-361 AND 50-362 1

Provide a comparison of key parameters (e.g., reactor coolant system (RCS) pressure, Tm ,, T,,,,, T , steam pressure, and steam generator (SG) outlet temperature) between the proposed operation with the T,,o reduction in your submittal and the design basis analysis.

2. Provide a summary of the evaluations (including analytical methodology, assumptions, and maximum stress and fatigue usage factors) for the effects of Too,o reduction on the i , structural and pressure boundary integrity of the reactor vessel and internals, RCS piping, control rod drive mechanisms and housing, pressurizer, surge line (stratification),

pressurizer spray nozzles, SGs, reactor coolant pumps, and pressurizer power-operated valves and safety valves. Identify changes in maximum stress and fatigue usage factors (at critical locations) from your evaluation.

i

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