ML17258A950

Forwards Safety Evaluation of Facility Inservice Insp Program for 1980-89 Interval.Program Is Acceptable If Plugging Limit for 10 Test Sleeves Is Established & Two Typographical Errors Are Corrected

ML17258A950
Person / Time
Site:	Ginna
Issue date:	04/04/1981
From:	Noonan V Office of Nuclear Reactor Regulation
To:	Novak T Office of Nuclear Reactor Regulation
Shared Package
ML13319A640	List: ML13319A639 ML13319A705 ML16138A447 ML17250A292 ML17250A294 ML17258A950 ML17338A640 ML17340A761 ML19273C366 ML19273D734 ML19275D923 ML20030A306 ML20031F023 ML20031F050 ML20031F059 ML20031F064 ML20031F069 ML20031F073 ML20031F076 ML20031F077 ML20031F080 ML20031F085 ML20031F102 ML20031F104 ML20031F111 ML20031F128 ML20031F130 ML20031F133 ML20031F138 ML20031F142 ML20031F147 ML20031F149 ML20031F153 ML20031F156 ML20031F157 ML20031F160 ML20031F162 ML20031F169 ML20031F174 ML20031F176 ML20031F180 ML20031F185 ML20031F189 ML20031F193 ML20031F195 ML20031F196 ML20031F199 ML20031F203 ML20031F211 ML20031F215 ... further results
References
FOIA-81-313 NUDOCS 8104130434
Download: ML17258A950 (6)

Text

APR 4 j98)

MEMORANDUM FOR:

Thomas H. Nova k. Assistant Director for Operating Reactors Division of Licensing FROM:

V. S. Noonan, Assistant Dil,'actor for Materials 8 qualifications Engineering Division of 'Engineering

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SUBJECT:

GINNA STATION STEAM GENERATOR TUBES INSERV ICE INSPECTION PROGRAM FOR THE 1 980'-1 989 INTERVAL (TAC 8431 96)

Plant Name:

R. E. Ginna Unit No.

1 Suppliers:

Westinghouse; Gilbert Associates Docket Number:

50-244 Responsible Branch and Project Manager:

ORB85; R. P. Snaider y Reviewer:

D. T. Huang Description of Task:

Review of Ginna Station's Steam Generator Tubes Inservice Inspection Program for the 1980-1989 Interval Review Status:

Additional Information Needed The Inservice Inspection Section of the Materials Engineering

Branch, Division of Enjineering has-reviewed that portion of Rochester Gas and Electric Corporation's submittal dated November 6, 1980 regarding the Ginna Station Steam Generator Tubes Inservice Inspection Program for the 1980-1989 interval.

We conclude in the basis of our review that the Ginna Station Steam Generator Tube Inservice Inspection Program for the 1 980-1 989 Inter val is acceptable if the fol1 owing two conditions are met:

1)

Plugging limit for the ten test sleeves be established.

2} '~f}I'ographlcal errors mentioned ln our Safety Evaluation be corrected.

Our Safety Evaluation is attached.

5$ 043S04S4 Vincent S. Noonan, Assistant Director Material s 5 gual ification s Engineering Division of Engineering

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R. E.

GINNA NUCLEAR POWER PLANT REVIEW OF THE STEAM GENERATOR TUBE INSERVICE INSPECTION PROGRAM FOR THE 1980 TO 1989 INTERVAL SAFETY EVALUATION REPORT MATERIALS ENGINEERING BRANCH INSERVICE INSPECTION SECTION INTRODUCTION By letter dated November 6, 1980, Rochester Gas and Electric Corporation (the licensee)

'submitted the "Ginna Station Inservice Inspection Program for the 1980-1989 Interval" for review.

Changes have been incorporated into Paragraph 5.7.1.1 and 6.5 of the Ginna Inservice Inspection Program in order to permit the installation of a maximum of ten test sleeves in steam generator tubes which would otherwise require plugging.

These changes permit sleeving instead of plugging of tubes with unacceptable defects.

EVALUATION We have reviewed the licensee's submittal dated November 6, 1980 regarding the Ginna Inservice Inspection Program.

Based upon our review, we conclude that this inspection program meets the recommendations of Regulatory Guide 1.83, "Inservice Inspection of Pressurized Water Reactor Steam Generator Tubes,"

'evision 1 and the requirements of Section XI of ASME Code with respect to the inspection methods to be used, provisions for a baseline inspections, selection and sampling of tubes, and inspection intervals.

However, the Ginna Inservice Inspection Program is incomplete with respect to the installation of ten test sleeves in steam generator

tubes, since it does not contain actions to be taken in the event defects are identified in the test sleeves, e.g.

plugging limit for the ten test sleeves.

Furthermore, two typographical errors should be revised to convey the same meaning regarding scope of

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1 steam generators inservice inspection as originally intended; They are as follows:

1.

The reference number in Paragraph 3.5 should be changed to 5 in order to be consistent with the reference list.

2.

Paragraph 5.7.1.1 should be revised to indicate that the plant may resume operation only when both conditions (a) and (b) are met.

In conclusion, we find that the steam generator tube inservice inspection portion of the "Ginna Station Inservice Inspection Program for the 1980-lg8g Interval" is acceptable with the condition that plugging limit for the ten test sleeves be established and the two typographical errors mentioned above be corrected.

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