ML20133H087

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Requests Ltr Stating That Listed Facilities Do Not Have Fuel Element Transfer Tubes.Documentation Needed for IE Bulletin 78-08 Closeout Rept
ML20133H087
Person / Time
Site: Millstone, Hatch, Monticello, Dresden, Peach Bottom, Browns Ferry, Nine Mile Point, Oyster Creek, Cooper, Pilgrim, Brunswick, Surry, Turkey Point, Vermont Yankee, Duane Arnold, Yankee Rowe, Quad Cities, Big Rock Point, Zion, FitzPatrick, 05000000, Trojan, Crane
Issue date: 10/10/1985
From: Lofy R
PARAMETER, INC.
To: Baer R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
CON-NRC-05-85-157-02, CON-NRC-5-85-157-2 IEB-78-08, IEB-78-8, NUDOCS 8510160264
Download: ML20133H087 (4)


Text

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S Pd FFE #[e rp 75c.

Since 1964 Mechanical Design and Analysis Consulting Engineers 13380 W ATERTOWN PLANK ROAD ELM GROVE, WISCONSIN 53122 414-786-7580 October 10, 1985 Mr. Robert L. Baer, Branch Chief Engineering & Generic Communications Branch Office of Inspection & Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Copies:

A. K. Barnold, w/ encl.

J. E. Wigginton, w/ encl.

References:

NRC Contract No. 05-85-157-02 PAR: NRC-157-02, Task 002

Subject:

Closeout of IE Bulletin 78-08:

Radiation Levels from Fuel Element Transfer Tubes Gentlemen:

The purpose of this letter is to request generation of a letter or memorandum stating that certain facilities which we have identified do not have fuel element transfer tubes.

Although we are confident that we have identified these facilities correctly, we need this documentation for the bulletin closeout report.

Referring to the first paragraph on Page 2 of IEB 78-08, note that facilities without these tubes are not required to respond.

In a recent conversation about another bulletin, Mary Wegner assured Walter Foley that no General Electric BWRs except Class 6 have fuel element transfer tubes.

La Crosse was not mentioned in that conversation.

Enclosed are three sets of copies of Pages B-3, B-7 and B-8 of the partially completed bulletin closeout report.

Notes 6 and 7 on Page B-3 refer to GE BWR Classes 1 through 4, Fort St. Vrain and La Crosse.

Table B.3 on Page B-7 lists class and product line numbers of GE BWRs.

References are listed on Page B-8.

Reference 4 is reserved in anticipation of the requested letter or memorandum.

If questions arise, please do not hesitate to call the writer or Walter Foley.

Very truly yours, 8510160264 851010

$DR ADOCK O 9

PARAMETER, Inc.

J RAL:mak Richard A. Lofy Enclosure President

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s TABLE B.1 (contd.)

Utility Closeout Facility NRC

Response

Inspection Status and Facility Utility Docket Status Region Date Report and Date Criterion _

Surry 1 VEPCO 50-280 OL II Open Surry 2 VEPCO 50-281 OL II Open TMI 1 Met-Ed 50-289 OL I

08-15-78 81-29(11-05-81)

Closed 3 See Note 4 TMI 2 Met-Ed 50-320 SDI I

08-15-78 See Note 4 Closed 1 Trojan PGE 50-344 OL V

See Note 5 Closed 3 Turkey Point 3 FPL 50-250 OL II 08-11-78 Open Turkey Point 4 FPL 50-251 OL II 08-11-78 Open Vermont Yankee 1 VYNP 50-271 OL I

See Note 4 Closed 2 Yankee-Rowe 1 YAECO 50-029 OL I

07-24-78 See Note 4 Closed 3 Zion 1 CECO 50-295 OL III Open Zion 2 CECO 50-304 OL III Open Notes for Table B.1:

T' 1.

Facility Status is based on Reference 1 Page B-8.

w 2.

The following abbreviations apply to facility status:

LPTL, Low Power Testing License; OL, Operating License; SDI, Shut Down Indefinitely.

3.

Refer to Page 4 for Bulletin Closeout Criteria.

4.

Refer to memorandum of August 30, 1978 for L. J. Cunningham (IE/HQ) from H. W. Crocker, Acting Chief, Fuel Facility and Material Safety Branch (RI).

5.

Refer to memorandum of August 24, 1978 for L. J. Cunningham (IE/HQ) from F. Wenslawski, Chief, Reactor Radiation Safety Section (RV).

6.

Refer to Table B.3, Note 2, Page B-7.

7.

Per Reference 4, Fort St. Vrain and La Crosse do not have fuel element transfer tubes.

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+

TABLE B.3 CLASS AND PRODUCT LINE NUMBERS OF AFFECTED GENERAL ELECTRIC BWRs Product Year Class Facility Class Line Introduced Big Rock Point 1 1

1955 Browns Ferry 1,2,3 4

67 1966 Brunswick 1,2 4

67 1966 Cooper Station 4

67 1966 Dresden 2 3

65 1965 t

Dresden 3 3

66 1965 Duane Arnold 4

67 1966 Fitzpatrick 4

67 1966 Hatch 1,2 4

67 1966 Millstone 1 3

65 1965 Monticello 3

66 1965 Nine Mile Point 1 2

63 1963 Oyster Creek 1 2

63 1963 Peach Bottom 2,3 4

67 1966 Pilgrim 1 3

66 1965 i

Quad Cities 1,2 3

66 1965 Vermont Yankee 1 4

67 1966 Notes for Table B.3:

1.

This information has been taken from Reference 3.

2.

Per Reference 4, these facilities do not have fuel element transfer tubes.

Closeout Criterion 2 applies.

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B-7

e REFERENCES

1. United States Nuclear Regulatory Commission, I.icensed Operating Reactors, Status Summary Report. Data as of 04-30-85, NUREG-0020, Volume 9, Number 5, May 1985
2. United States Nuclear Regulatory Commission, Code of Federal Regulations, _ Energy, Title 10, Chapter 1, January 1, 1984, cited as 10CFR 0.735.1
3. United States Nuclear Regulatory Commission Reactor Training Center, Technolory Manual, Boiling Water Reactors. BWR/6 Design 7
4. United States Nuclear Regulatory Commission, Memorandum....

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