ML17258A560

Informs That Schedule for Performing Analyses of Code Changes That Could Have Decreased Margins of Safety Will Be Submitted by 820531,per NRC 811230 Ltr Forwarding Draft Ser. Containment Vessel Evaluation Encl

ML17258A560
Person / Time
Site:	Ginna
Issue date:	02/18/1982
From:	Maier J ROCHESTER GAS & ELECTRIC CORP.
To:	Crutchfield D Office of Nuclear Reactor Regulation
Shared Package
ML17258A561	List: ML17258A560 ML17258A562
References
TASK-03-07.B, TASK-3-7.B, TASK-RR NUDOCS 8202240083
Download: ML17258A560 (6)

Text

g j 1 REGULATORY

'RMA'T ION DISTRIBUTION SYS l ('RIDS)AOCESSION NBR:8202240083-DOC~DATE: 82/02/18 NOTARIZED:, NO DOCKET¹FACIL:50-'244 Robert Emmet Ginna Nuclear Plantr'Uniit ii.'Rochester G 05000244'AUTH.NAl1E AUTHOR AFFILIATION MAIERg J~E~'Rochester

'Gas 8>Electric'Corp'EC IP~NAME RECIPIENT AFFILIATION CRUTCHFIELDg D, Operating Reactors Branch 5

SUBJECT:

Informs)that schedule for performing, analyses of code changes>that could have>decreased margins of>safety will'be submitted by 820531iper NRC 811230 ltr forwording draft SER.Containment vessel evaluation encl'ISTRIBUTION CODE: A035S COPIES IRECEIVED:LTR, ENCL,'SIZE:,~'TITLE: SEP Topics NOTES: 1 copy:SEP Sect.Ldr~05000244 RECIPIENT ID CODE/NAM>E ACTION: ORB¹5 BC 01 INTERNAL: IE 06 NRR/DE/HGEB 10 NRR/DL/SE'PB 12 NRR/DSI/CSB 07>COPIES LTTR ENCL 7%7 2'2 2"2 3 3 1" 1'REC IP IENT ID CODE/NAME NRR/DE/ADMQE 13 NRR/DL/DRAB 11 N G I'04>COPIES LTTR ENCL 1 1 1-1 1 1 1 1 ,EXTERNAL:

ACRS 14 NRC PDR 02 10 10 1, 1 LPDR NTIS 03 v5 TOTAL-NUMBER OF COPIES REQUIRED: L~TTR~ENCL 4, t'l'1 I>><r M p'l e ee==a 6 1 i i EIIIIIIII/

El/IIIIII A rrD/IIIIIIIIIII/I I//I/IIIIIIII/

ROCHESTER GAS AND ELECTRIC CORPORATION

~89 EAST AVENUE, ROCHESTER, N.Y.14649 JOHN E.MAIER Vice President TKI,KPHONK ARKA cooK Tie 546.2700 February 18, 1982 Director of Nuclear Reactor Regulation Attention:

Mr.Dennis M.Crutchfield, Chief Operating Reactors Branch No.5 U.S.Nuclear Regulatory Commission Washington, D.C.20555

Subject:

SEP Topic III-7.B,"Design Codes, Design and Loading Combinations" R.E.Ginna Nuclear Power Plant Docket No.50-244 I

Dear Mr.Crutchfield:

This letter is in response to your letter of December 30, 1981, transmitting the draft Safety Evaluation Report for this topic, as well as two contractor reports which formed the bases for the SER.The first contractor report, Franklin Research Center draft Technical Evaluation Report TER-C5257-322,"Design Codes, Design Criteria, and Loading Combinations," identifies code changes that have occurred that.could have decreased margins of safety.RG&E was requested to assess the safety margins where such code changes have been identified.

This is a substantial task, requiring the review, comparison, and analysis of major sections of the ASME, AISC, and ACI Codes.We have not yet been able to assess the full scope of effort needed to perform this evaluation.

It is expected that a schedule for performing the necessary analyses will be submitted to the NRC by the end of May, 1982.The second contractor report, Structural Mechanics Associates Report SMA 12205.27R,"Combined Loads Evaluation," dated December 1981, addresses a potential containment liner plate integrity problem.The enclosed Gilbert/Commonwealth report,"Containment Vessel Evaluation," responds to the SMA report.The conclusion of the G/C report is that.the structural integrity of the studs and liner would be maintained.

.(,.('8202240083 8202i8 PDR ADOCK 05000244 I: 'I',P,,:,,;..',,;.PDR;.

I fl'I I y s lb ROCHESTER GAS AND ELECTRIC CORP.oATE February 18, 1982 Mr.Dennis M.Crutchfield SHEET NO.It should be noted that the specific G/C analysis was per-formed for a post-accident.

pressure-temperature profile which was calculated by G/C (see Figure 3 of the report).This corresponds fairly closely to the Ginna FSAR curves and the August 1981 SMA preliminary draft report.(A February 1, 1982 RG&E letter relative to SEP Topics VI-2.D and VI-3 notes that the steam line break conditions used as the basis, for the December 1981 SMA report are excessively conservative to use as a design basis).Further, the G/C report primarily evalutes this August 1981 SMA report, rather than the December 1981 report.However, the conclusion of the G/C report, provided in Sections V and VI, is that the containment liner and stud integrity would be maintained, even using these overly-conservative NRC steam break conditions.

Very truly yours, Jo n.Maier 1 t