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CORRESPONDENCE-LETTERS  and INCOMING CORRESPONDENCE

ANSIB16.5 +  and ANSIB31.1 +

Boron +, Cobalt +, Iron +, Nickel +, Carbon +, Oxygen +, Hydrogen +, Chloride +, Lead +, Lithium +, Manganese +, Chromium +  and Tin +

10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.49 +, 10 CFR 50.61 +, 10 CFR 50.49w#a +  and 10 CFR 50.54#f +

S.3(p) +  and S.2(p) +

05000244  +, 00244  +  and 00485  +

Rochester Gas and Electric +  and MECREDY R C +

GDC 33 +, GDC 57 +, GDC 20 +, GDC 38 +, GDC 41 +, GDC 44 +, GDC 34 +, GDC 15 +, GDC 50 +, GDC 16 +, GDC 54 +, GDC 10 +, GDC 12 +, GDC 55 +, GDC 56 +, GDC 61 +, GDC 35 +, GDC 14 +, GDC 60 +, GDC 18 +, GDC 21 +, GDC 24 +, GDC 11 +, GDC 13 +, GDC 30 +, GDC 46 +, GDC 31 +, GDC 39 +, GDC 45 +, GDC 40 +...

ML17309A609 +, ML17309A609 +, ML17309A609 +, ML17309A609 +, ML17309A609 +, ML17309A609 +, ML17309A609 +, ML17309A609 +, ML17309A609 +, ML17309A609 +, ML17309A609 +, ML17309A609 +  and ML17309A609 +

IEEE 279-1971 +, IEEE 308-1971 +, IEEE 336-1971 +, IEEE 338-1971 +  and IEEE 334-1971 +

Westinghouse +  and Foxboro +

NRC Bulletin 79-14 +, NRC Bulletin 88-11 +, NRC Bulletin 85-03 +, NRC Bulletin 88-02 +  and NRC Bulletin 79-13, Cracking in Feedwater System Piping +

NUREG-0944, Notice of Availability of SER for full-term OL (NUREG-0944) +, NUREG/CR-0200 +, NUREG/CR-2569 +, NUREG/CR-2580 +, NUREG-0612, Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley +, NUREG/CR-0098, Forwards SEP Position Re Consideration of Inelastic Response Using NUREG/CR-0098 Ductility Factor Approach,Providing Addl Guidance Regarding Application of Ductility Methodology +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG/CR-1389, Forwards Fr Notice of Issuance & Availability of NUREG/CR-1389, Estimating Water Equivalent Snow Depth from Related Meteorological Variables, & NUREG/CR-1390, Probability Estimates of Temp Extremes for Contiguous Us +, NUREG-0569, Forwards NUREG-0569, Evaluation of Integrity of SEP Reactor Vessels, Completing Review of SEP Topic V-6.W/o Encl +, NUREG-0821, Forwards Safety Evaluations of SEP Topics,Vols I-III,per App E of NUREG-0821, Integrated Plant Safety Assessment Rept for Re Ginna Nuclear Power Plant +, NUREG/CR-1821, Forwards List of Open Issues from Draft NUREG/CR-1821, Seismic Review of Robert E. Ginna Power Plant as Part of Sep. Addl Info Re Seismic Design Consideration & Component Integrity Should Be Submitted within 30 Days +  and NUREG/CR-1821.20 +

TAC:M93827 +, TAC:M92188 +, TAC:M83733 +, TAC:75131 +  and TAC:67304 +

2r-d +, 622B-632B-642B-652 +, 123B-1338143 +, 33D-43D-53D-63 +, 1steam-drivena +, 000gpd-Filtrat +, A1F-GDC59 +, 601non-radioac +, 5c-5d +, 5S-S +, 2b-in +, 000MS-8Safesh +, 250S-60verti +, 250S-135vert +, 750S-135axia +, 750S-145vert +, 750S-210axia +, 750S-225vert +, 950ft-lbtempe +  and 71Oa0a-19 +

Texas +, Pennsylvania +, Connecticut +, Washington +, California +, Massachusetts +, Alabama +, Michigan +  and Oregon +

NRC (Affiliation Not Assigned) +, VISSING G +  and Office of Information Resources Management +

Earthquake +  and Leak-Before-Break +

F-48hr-FC1100-1125 +, F-22hr-AC1210 +, F-30hr-FC1125 +, F-12hr-AC1125 +, F-18hr-AC1100 +, F-9hr-AC1220 +  and F-11hr-FCForgingsNote +