ML18142C028

Letter Submitted Application for Amendment to Technical Specification, Consisting a Request for a Change to the License Maybe Amended to Add Inspection Requirement for Steam Generator Tubes

ML18142C028
Person / Time
Site:	Ginna
Issue date:	10/15/1974
From:	Babcock H, White L LeBoeuf, Lamb, Leiby & MacRae, Rochester Gas & Electric Corp
To:	Case E US Atomic Energy Commission (AEC)
References
Download: ML18142C028 (20)

Text

AEC DISTRIBUTION FOR PART 50 DOCKET MATERIAL (TEMPORARY FORM)

CONTROL NO:

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20036 DA'TE OF DOC 10-15-74 DATE R EC'D LTR 10-15-74 TWX RPT OTHE R TO:

Mr. Case ORIG 1 signed CC OTHER SENT. AEC PDR X

SENT LOCAL PDR CLASS UNCLASS PROPINFO XXX INPUT NO CYS REC'D DOCKET NO:

50-244 DESCRIPTION:

Ltr submitted on behalf of the Rochester Gas

& Elec. Corp......re our 7-18-74 ltr....

trans the following:

gi(I;(P;le()IlI'.II Oo @of Rar3oiio PL"ANT NAME:

R. E. Ginna Unit 0 1

ENCLOSURES:

A 1 for Amdt to'ech S ecs notarized 10-14-74, consisting a request for a change to the Tech Specs so that the Lic may be amended to add an inspection requirement for steam generator tubes CERTIFICATE OF SERVICE showing svc of"Appl for Amdt to Tech Specs",

upon B. E. Thompson, Supervisor, Town of Ontario, NY FOR ACTION/INFORMATION 10<<17-74 BUTLER (L)

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'IIaguI'.eP LAW OFFICES OF LEBOEUF, LAMB,LEIBY 8 MACRAE I757 N STREET;N.W.

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'RVIN E. UPTON LEONARD M. TROSTEN WILLIAM9. DOUB IADM.NARVLANa)

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HARRY H VOIGT LKX K ~ I.ARSON WASHINGTON PARTNCRS October 15, 1974 I

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Mr. Edson G.

Case Acting Director Directorate of Licensing U.S. Atomic Energy Commission Washington, D.C.

20545 ONC CHASE MANHATTANPLAZA NEW YORK, N. Y. IOOOS WASHINGTON TCLCPHDNC 202 872-8668 CADI.C ADDRESS LALALII,WASHINGTON D.C.

Re:

Rochester Gas 6 Electric Corporation R. E. Ginna Nuclear Power Plant, Unit Mo.

1 Docket Mo. 50-244

Dear Mr. Case:

Transmitted herewith are three (3) signed originals and nineteen (19) copies of Rochester Gas

& Electric Cor-poration's Application for Amendment to Technical Specifi-cations and forty (40) copies of the proposed change.

A safety evaluation of the proposed change is also transmit-ted.

The proposed change will add an inspection require-ment for steam generator tubes in response to a letter from Karl E. Goller, Assistant Director for Operating Re-

actors, dated July 18, 1974.

A Certificate of Service is also enclosed.

Enclosures Very truly yours, 45IKIIJI, 4uu b, 4dq ~ %4+~

LeBoeuf, Lamb, Leiby 6 MacRae Attorneys for Rochester Gas S

OOCXIYEO UQEC Electric Corporation tl QQQ gy ~gyes C

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UNITED STATES OF AMERICA ATOMIC ENERGY COMMISSXON In the Matter of

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ROCHESTER GAS 6 ELECTRIC CORPORATION

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(R.E. Ginna Nuclear Power Plant,

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Sect(gy Docket No. 50-244 APPLICATION FOR AMENDMENT TO TECHNXCAL SPECIFICATIONS Pursuant to Section 50.90 of the regulations of the Atomic Energy Commission, Rochester Gas and Electric Corpor'ation

("RGGE"),

holder of Provisional Operating License No. DPR-18, hereby requests that, the Technical Specifications set forth in Appendix A to that license be amended to add an inspection requirement for steam generator tubes in response to a letter from Karl E. Goller, Assistant Director for Operating Reactors, dated July 18, 1974.

The proposed technical specification change is set forth in Attachment A to this application.

A safety evaluation, which demonstrates that the proposed change does not involve a significant hazards consideration, is set forth in Attachment B.

The proposed change would not authorize any change in the types or any increase in the amounts of effluents or any 'change in the authorized power level of the facility.

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WHEREFORE, Applicant respectfully request that Appendix A to Provisional Operating License No.

DPR-18 be amended in the form attached hereto as Attachment A.

ROCHESTER GAS Sr ELECTRIC CORPORATION By Leon D. Wh3.te, r.

Vice President, Electric and Steam Production Subscribed and sworn to before me on this l//~day of October, 1974 otary Public GARY L. REISS IIQTAQY PUBLIC, State of fi. Y. h1onroo Co.

My. Commission Expires March 30, 19.Z~

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ATTACHM'NT A Add the following to Section 4.2, Primary Component Tests:

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Table 4.2-1 page 4.2-2 add line d. to D. Steam Generator, as below Component; 6

Examination Area Sample Inspection Process Extent and Frequency D.

d. tubes EC or UT m.

II.

Notes page 4.2-4 add to note l. as follows EC Eddy Current IXI.

Notes page 4.2-7 add a paragraph

m. to note 2 as follows:

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The tubes of each steam generator shall be examined as follows:

l.

Inspection Xntervals Inservice inspection of steam generator tubes shall be performed at intervals of not more than 20 months.

Xf at least 2 inspections of the separate legs covering a nominal 2 year period (e.g.,

two normal fuel cycles) result C

in no additional tubes with detectable wall penetration

()20%)

and no significant

()5-o) further penetration of tubes with previous indications the inspection frequency of the individual legs may be decreased to at least

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0 once every 40 months for hot 3begs and at least once every 10 years for cold legs.

An inspec-tion of a limited nunher of tubes shall be conducted at the next refue ling in the event of primary to secondary leaks which exceed tech-nical specification limits.

Special inspections of a limited number of tubes shall be conducted before standup in the event. of a seismic occurrence greater t3aan that, for which the plant is designed to continue operation, a major steam line or feed water line break, or a loss-of-coolant; accident which imposes a signi-ficant pressure transient on the steam generators and requires actuation of engineered safeguards.

2.

Tube Selection The extent.

and selection of steam generator tube examinations for scheduled inspections shall be as described in USAHC Regulatory Guide 1.83 sections C.4 and C.5 with the interpretation that examination of all previously defective tubes

(>20% detectable wall penetration) and two hundred previously defect-free tubes

((20-o-C detectable wall penetration) is deemed sufficient, but not necessary, to meet this criteria.

3.

Acceptance Limits

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3.1 l If in the inspection in 2, (a) less than 10%

of. the inspected tubes have developed detec-table wall penetration (5208) in previously defect-free tubes

(<20% wall penetration) or exhibit significant further wall penetration

(

5%) of previous defects, and (b) no tube has an unacceptable tube wall thickness, plant operation may resume.

An unacceptable tube wall thickness is one which cannot sustain a

LOCA in combination with a seismic occurrence for which the plant is designed to continue operation without a loss of function of Class I systems.(

3.2 Xf no more than 3 tubes have unacceptable tube wall thickness, but the above criteria are otherwise met,, plant operation may resume after corrective measures have been taken.

3.3 If the criteria of 3.1 or 3.2 are not met, tne situation shall be reported as an abnormal occurrence.

Plant operation may resume after corrective measures have been taken.

IV.

Basis page 4.2-9 add to basis as follows:

The inspection program for steam generator tubes is designed to meet the guidance provided in the USAEC Regulatory Guide 1.83, Xnservice Inspection of Pressurized Nater Reactor Steam Generator Tubes.

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Reference add the following reference (2)

PSAR S'ection 2.9.3

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ATTACHMENT 8 Safet Evaluation A program of steam generator tube inspection is proposed which should provide adequate assurance of acceptable steam generator performance.

The program, which is designed to meet the guidance provided in USAEC Regulatory Guide 1.83, calls for inspections at regular intervals of steam generator tubes in each leg of each steam generator and sets acceptance criteria on acceptable tube wall thickness.

The acceptance criteria are selected to assure acceptable performance in the unlikely event of a design basis condition.

BEFORE THE UNITED STATES ATOMIC ENERGY COMMISSION

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In the Matter of

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Rochester Gas

& Electric Corporation

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(R. E. Ginna Nuclear Power Plant,

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Unit. No. 1)

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Docket. No. 50-244 CERTIFICATE OF SERVICE I hereby certify that I have served a document. entitled "Application for Amendment. to Technical Specifications" by mailing copies thereof--"first class, postage prepaid, to each of the following persons this 15th day of October, 1974.

Chairman, Atomic Safety and Licensing.Boards Panel U.S. Atomic Energy Commission Washington, D.C.

20545 Atomic Safety and Licensing Appeal Board U.S. Atomic Energy Commission Washington, D.C.

20545 Mr. Michael Slade 1250 Crown Point Drive

Webster, New York 14580 Warren B. Rosenbaum, Esq.

One Main Street East 707 Wilder Building Rochester, New York 14614 C. John Clemente, Esq.

'.New York State Department of Commerce 99 Washington Avenue

Albany, New York 12210 Howard M. Wilchins, Esq.

Counsel, Regulatory Staff U.S. Atomic Energy Commission Washington, D.C.

20545 Edward Luton, Esq.

Atomic Safety and Licensing Board Panel U.S. Atomic Energy Commission Washington, D.C.

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Thomas W. Reilly, Esq.

Atomic Safety and Licensing Board Panel U.S. Atomic Energy Commission Washington, D.C.

20545 Dr. Franklin C. Daiber Department of Biological Sciences University of Delaware Newark, Delaware 19711 Dr. A. Dixon Callihan Union Carbide Corporation P.

O. Box Y Oak Ridge, Tennessee 37830 Mr. Bruce E. Thompson Supervisor, Town of Ontario 528 Furnace Road

Ontario, New York 14519 Dr. Emmeth A. Luebke Atomic Safety and Licensing Board Panel U.S. Atomic Energy Commission Washington, D.C.

20545 Hope M. Babcock

LeBoeuf, Lamb, Leiby 6 MacRae Attorneys for Rochester Gas 6 Electric Corporation

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