ML18142A833

R. E. Ginna - Fission Gas Release Model

ML18142A833
Person / Time
Site:	Ginna
Issue date:	02/24/1977
From:	White L D Rochester Gas & Electric Corp
To:	Schwencer A Office of Nuclear Reactor Regulation
References
Download: ML18142A833 (4)

Text

U.S.NUCLEAR REGULATORV C ISS ION l D NRC FoRM 19a~~-(2 76), ,"NRC DISTRIBUTION FOR PART 50 DOCKET MATERIAL DOCKET NUMBER 50-244 FILE NUMBER TO.r'r.A.'Schwencer FROM: Rochester Gas&Electric Company Rochester, New York L.D.White Jr.DATE OF DOCUMENT 2/24/77 DATE RECEIVED 2/28/77 JR[LETTER goR IG INAL 0copv~DESCRIPTION ONOTORIZED QUNC LASS IF I E D PROP INPUT FORM ENCLOSURE NUMBER OF OPIES RECEIVED One signed Ltx'.re oux'l/29/76 ltr.and their 1/3/77 ltr....regarding fuel fission gas release models.....

DO<<>aZXroyg PLANT NAME'.E.Ginna Unit No.1 (1-P)~CK><>VLmaza SAFETY FOR ACTION/INFO RMAT I ON RJL ASSIGNED AD: K RO ECT MANA E LIC ASST Goller Schwencer Wambach.She ard PROJECT hfANAGERi LIC ASST REG FQL NRC PDR I,&.E OELD GOSSICK&STAFF MIPC CASE HANAUER 1Q RLESS PROJECT MANAGEMENT BOYD PE COLLINS HOUSTON PETERSON MELTZ HELTEMES SKOVHOLT LPDR TIC: NSIC: ASLB: ACRS CYS NRC FORM 195{2.76)INTERNAL D SYSTEMS SAFETY-.HEINEMAN SCHROEDER ENGINEERING MACARRY BOSNAK SIHWEIL PAWLICK REACTOR SAFE ROSS NOVAK ROSZTOCZY CH CK AT&SALTZMAN RUTBERG EXTERNAL DISTRIBUTION NAT LAB~REG V IE LA PDR CONS TANTS ISTRI BUTION PLANT SYSTEMS TEDESCO 0 IPPOL TO OPERATING REACTORS STELLO OPERATING CH EISENHUT B,E ULRIKSON OR S TE SAFE ERNST BALLARD SPANGLER SITE TECH'AMhfILL STEPP HULhfAN SITE ANALYSIS VOLLMER BUNCH J COLLINS KREGER CONTROL NUMBER

~>rr 4 er 4~7~-~~~~I~~e~f~0~e/e eI 4 h 7 h r ff ZznZXPt g ZZZZ!Z<'g~iirr zvuu~iran~uiruuu ROCHESTER GAS AND ELECTRIC CORPORATION I'hh7 II I-h h III~h hh~0>>I S Se h=~I 7 roar ITAIC I'.o 89 EAST AVENUE, ROCHESTER, N.Y.14649 LEON D.WHITE.JR.VICE PRESIDENT TELEPHONE AREA CODE 7IS 546-2700 February 24, 1977 Director of Nuclear Reactor Regulation ATTN: Mr.A.Schwencer, Chief Operating Reactors Branch 41 U.S.Nuclear Regulatory Commission Washington, D.C.20555

Subject:

Fission Gas Release Model R.E.Ginna Nuclear Power Plant, Unit No.1 Docket No.50-244 Dear Mr.Schwencer; This letter is in response to your letter of November 29, 1976 and, supplements our initial response dated January 3, 1977 regarding fuel fission gas release models.In our January 3, 1977 letter we provided the results of calculation performed by Westinghouse Electric Corporation which demonstrated that the internal pressure of all Westinghouse fuel presently in the reactor would remain well below the system pressure for the period of operation until the next refueling stage.In addition, we reported that the internal pressure of the two Babcock and Wilcox fuel assemblies, which will be permanently discharged at the next refueling, would remain well below system pressure until that time.At the time of our initial response, calculations had not yet been performed for the two Exxon Nuclear Company fuel assemblies, which are presently in their third cycle.Calculations have now been completed which confirm the fact that the internal pressure of these two assemblies, which are also scheduled for discharge at the next refueling, will remain well below system pressure until that time.Very truly yours, 2022 L.D.White, Jr.UiSg IIIICLEAII REQIIt'AT 5 COMM I5$IOM 6' Jf H J'L C~Cj.7z tg