ML18190A167

R. E. Ginna - Enclosed Copy of Reactor Vessel Fabrication & Inspection Information Requested by Mr. K. G. Hoge. Listed Various Inspection Reports & Dates for Documentation

ML18190A167
Person / Time
Site:	Ginna
Issue date:	07/27/1978
From:	White L Rochester Gas & Electric Corp
To:	Ziemann D Office of Nuclear Reactor Regulation
References
Download: ML18190A167 (8)

Text

~., P~ >yy IIIIIIIW IIIIII IIII/f8Ãl/III ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. 14649 J

LEON D, WHITE. JR. TELEPHONE VICE PRESIDENT ARE* CDDE TIS 546-2700 July 27, 1978 Director of Nuclear Reactor Regulations Attention: Mr. Dennis L. Ziemann, Chief Operating Reactor Branch No. 2 U.S. Nuclear Regulatory Commission r~

Washington, DC 20555 Cw'I C'lr-t

Subject:

Reactor Vessel Fabrication and rrP

)

Inspection Information I I

CTI Cn~D R. E. Ginna Nuclear Power Plant Unit No;,~l'> C=.W Docket No. 50-244 MC TT I

Dear Mr. Ziemann:

E4 Enclosed herewith please find a copy of the fabrication and inspection information requested by Mr. K. G. Hoge of your staff.

The following information list the various inspection reports and their dates for your documentation.

a) "Ultrasonic Inspection of Rochester Gas and Electric Cor-poration Nuclear Reactor"; BaW Fabrication Contract 610-0110; BSW Report No. 615; January 26, 1968.

b) . "Robert E. Ginna Nuclear Power Station Preoperational In-spection Report"; SWRI Project 17-2376; Final Report; January 1972.

c) "1971 Inservice Examination of the Robert E. Ginna Nuclear Power Station"; SWRI project 17-3074; July 1972.

d) "1972 Inservice Examination of the Robert E. Ginna Nuclear Power Station"; SWRI project 17-3377; July 1972.

e) "1974 Inservice Examination of Class 1 Components at the R. E. Ginna Nuclear Power Station"; SWRI Project 17-3874; September 1974 f) "1975 Inservice Examination of Class 1 Components at the R. E. Ginna Nuclear Power Station"; SWRI Project 17-4206; June 1975.

We hope this information is helpful to your staff.

Very truly yours, I,782120043 L. D. White, Jr. ~-----

Ginna Station Reactor Vessel Governing Specifications

1. The American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section III, "Rules for Construction of Nuclear Vessels."

1965 and applicable code cases for Class A vessels.

Code Cases U er Shell'ourse 1332-1 Shell is fabricated of SA-336 manganese-molybdenum steel.

Lower Head Rin 1332-1 Ring is fabricated of SA-336 maganese-molybdenum steel.

2. The American Society of Mechanical Engineers, Boiler and Pressure Vessel Code,Section IX, Welding Qualifications, 1965.

3. ASA B31.1, Code for Pressure Piping,Section VI, Chapter 3 (1955).

Westinghouse Atomic Power Division Equipment Specification E-676206 except as ammended by .Westinghouse Electric Corporation, Atomic Power Division Contract No. 54-Q-49758-BP dated November 15, 1965.

5. The Babcock 6 Wilcox Company, Quality Control Department Specifications covering: Welding, Nondestructive Testing, Heat Treating, Cleaning and Testing.

Nondestructive Examinations Performed on Vessel A manual Ultrasonic Examination was performed on the reactor vessel at the Ginna Power Station location on December 4 through December 9 and December 18 through 22, 1967. The examination was performed by representa-tives of Babcock and Wilcox Quality Control N.D.T. Section. This examina-tion was performed in accordance with the requirements specified by Westing-house Atomic Power Division.

The closure head was examined at BGW Co., Mt. Vernon, Indiana Works on November 29 and 30, 1967.

In August 1969, Southwest Research Institute was contracted to perform preservice nondestructive examination on selected components, including the reactor vessel at Ginna, prior to the system's startup. These examinations were performed to evaluate the overall structural integrity of the system and to provide baseline information for subsequent inservice examination comparisons. A mechanized ultrasonic technique was employed. The procedure and sensitivity requirements for the examination were derived from South-west's experience and are in accordance with Section III, Appendix IX of the ASME Code.

VlrJl~bVLNL'4 &Ajar'jLlltklLVLV aurjL'utah - tczAL July l'ithbbUKh VESSEL ROBERT E. GINNA NUCLEAR POWER STATION DATE E3QQfINATION AREA IDENTIFICATION RESULTS 1967 BSM Closure head - from the cooling shroud to the No Recordable Indications flange radius Vessel Flange No Indications Vessel flange to upper shell weld No Recordable Indications Vessel upper shell to Intermediate shell weld 23 minor indications (less than 100% .

reference level.) (Shearwave)

Vessel Intermediate shell to lower shell weld No Recordable Indications Vessel lower shell course above radial core supports 5 minor indications (less than 60$

reference level.) (Shearwave)

Primary coolant nozzles No Recordable Indications Nozzle to nozzle shell cour'se welds one indication (405 of ref. level) Noz B (Safety injection nozzles) two indications (70Ã of ref. level) Noz A

ua,xsvaav[vxv r mmxi~rax <vis auto'usa> l<nil LVK i Kj;bbUKh Vj'bbr L ROBERT E. GINNA NUCLEAR POWER STATION DATE EXVfINATION AREA IDENTIFICATION RESULTS 1969 SwRI Vessel-to-Flange circumferential weld No Significant Indications Head to Flange circumferential weld No Si gni ficant Indi cati ons Upper shell to intermediate shell circumferential weld No Indications Intermediate shell to lower shell circumferential weld No Indications Lower shell to ring forging No Indications circumferential weld Ring forging to lower head weld No Indications Primary nozzle to vessel welds No Indications Loop A - Inlet Loop A - Outlet No Indications Loop 8 - Inlet No Indications Loop 8 - Outlet No Indications Primary nozzles to safe end welds No Indications Loop A - Inlet Loop A Outlet No Significant Indications ~ ~

Loop 8 - Inlet No Indications Loop 8 - Outlet No Significant Indications

us lxmbUllil I'luviLnniivn oueuvuii - 5~1 lute t'r LDDUkcl VLobf L ROBERT E. GINNA NUCLEAR POWER STATION DATE EE&HNATION AREA IDENTIFICATION RESULTS 1969 Primary nozzle high strain areas No Indications Closure head studs (48 studs) No Indications Closure head cladding 8 - 6" x 6" patches (PT) No Indications 1971 SwRI Head to Flange circumferential welds . No Indications Closure head studs (48 studs) No Indications Closure head nuts (48 nuts) No Indications 48 Ligament areas between flange stud holes No Indications Flange to Upper shell circumferential weld. No Indications 1972 SwRI Closure head studs (48 studs) No Indications Closure head nuts (48 nuts) No Indications

ul lnAbul'ilL I'Mill'iniluil~vrlrvwxl a(Gtil Iud( i 5LboUM vkbaf 4 ROBERT E. GINNA NUCLEAk POWER STATION DATE E3QQfINATION AREA IDENTIFICATION RESULTS 1974 SwRI Vessel to flange circumferential weld No Recordable Indications Head to flange circumferential weld No Recordable Indications Control rod drive penetrations (VT) No Indications Closure head studs (48 studs) No Recordable Indications Closure head nuts (48 nuts) No Recordable Indications Closure head washers (VT) (48 washers) No Indications Interior surfaces and internals and integrally-welded internal supports (VT)

Vessel flange ligaments between each stud hole No Indications Closure head cladding (PT) 2 6" x 6" patches No Indications 1975 SwRI Nozzle to vessel weld Loop A - Outlet Insignificant Indications Nozzle inside radius section .Loop A - Outlet No Recordable Indications Nozzle to safe end weld - Loop A - Outlet No Recordable Indications

ULltCADUlVJL L'~'LLiVALLVL> burumiCz ~u.ivK rheaauwr. Vsaoec ROBERT E. GINNA NUCLEAR POWER STATION DATE ERQ1INATION AREA IDENTIFICATION RESULTS 1975 SwRI Nozzle to vessel weld - Loop 8 - Outlet Insignificant Indications Nozzle inside radius section Loop 8 - Outlet No Recordable Indications Nozzle to safe end weld - Loop 8 - Outlet No Recordable Indications Safety injection nozzle to vessel weld No Recordable Indications Loop A Safety injection nozzle inside radius section- No Recordable Indications Loop A Safety injection nozzle to vessel weld Loop 8 No Recordable Indications Safety injection nozzle inside radius section- No Recordable Indications Loop 8 Closure head studs (48 studs) No Recordable Indications Closure head nuts (48 nuts) No Recordable Indications Closure head washers (48 washers) (VT) No Recordable Indications

ULlKASONLC hXAHLHALJ.UN SUE'1t'IAK> K~l'TOK k'KESSUKE VESSEL ROBERT E. GINNA NUCLEAR POWER STATION DATE E)URINATION AREA IDENTIFICATION RESULTS 1978 SwRI Vessel flange ligaments between threaded stud holes No Recordable Indications (1/3 of the ligaments examined)

Head-to-flange circumferential weld. No Recordable Indications (1/3 of the length of weld examined)

Closure head studs (16 studs) (UT,HT) Insignificant Indications Closure head nuts (16 nuts) (UT,NT) No Significant Indications Closure head washers (16 washers) (VT) No Recordable Indications Closure head cladding (2 - 6" x 6" patches examined) No Recordable Indications (PT,VT)