ML17263A171

Forwards 30-day Response to Suppl 1 to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount, Consisting of Tabulation of Rosemount Transmitters Installed at Facility

ML17263A171
Person / Time
Site:	Ginna
Issue date:	03/05/1993
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	Andrea Johnson Office of Nuclear Reactor Regulation
References
IEB-90-001, IEB-90-1, TAC-M76559, NUDOCS 9303110210
Download: ML17263A171 (10)

Text

ACCELERAT+DOCU1VIENT DISTRI TION SYSTEM REGULATOR> INFORMATION DISTRIBUTION S TEM (RIDS) 1 ACCESSION NBR:9303110210 DOC.DATE: 93/03/05 NOTARIZED: YES DOCKET ¹ FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G

05000244 AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.

Rochester Gas a Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION

'JOHNSON,A.R.

Project Directorate I-3

SUBJECT:

Forwards 30-day response to Suppl 1 to NRC Bulletin 90-001, "Loss of Fill-Oil in Transmitters Mfg by Rosemount,"

consisting of tabulation of Rosemount transmitters installed at facility.

DISTRIBUTION CODE:

IE39D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: NRC Bulletin 90-001, Loss of Fill Oil in Transmitters Mfg b Rosemoun NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).

05000244 RECIPIENT ID CODE/NAME PD1-3 PD INTERNAL: NRR LEgN NRRg~C REG FILE 02 RGN1 ILE 01 COPIES LTTR ENCL 1

1 1

1 1

1 1

1 1

1 RECIPIENT ID CODE/NAME JOHNSON,A NRR/DORS/OGCB NRR/OEAB RES/EMEB COPIES LTTR ENCL 1

1 1

1 2

2 1

1 EXTERNAL: NRC PDR

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1 NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE( CONTACI'HE DOCUMENT CONTROL DESK, ROOM PI-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISIS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED:

LTTR 12 ENCL 12

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89 EAST AVENUE, ROCHESTER N.Y. 1464g-OOOO ROBERT C. MECREDY Vice President Cinna Nuclear Production March 5, 1993 TEt.EPHONE ArcEACtXrE P ttt 546-2700 U.S. Nuclear Regulatory Commission Document Control Desk Attn:Allen R. Johnson PWR Project Directorate I-3 Washington, D.C.

20555

Subject:

Response

to NRC Bulletin No. 90-01, Supplement 1 dated December 22, 1992 Loss of Fill-Oil in Transmitters Manufactured by Rosemount R.E.

Ginna Nuclear Power Plant Docket No. 50-244 Ref.(a):

Letter from R.C.

Mecredy (RG&E) to A.R. Johnson (NRC),

"Response to Bulletin 90 01P dated May 29P 1990 (b):

NRC Bulletin No. 90-01:

Loss of Fill-oilin Transmitters Manufactured by Rosemount, dated March 9, 1990 (c):

Letter from A.R. Johnson (NRC) to R.C.

Mecredy (RG&E),

"Closeout of Bulletin 90-01 (TACN6559)," dated December 4,

1990

Dear Mr. Johnson:

This letter provides RG&E's 60-day response to NRC Bulletin

,90-01, Supplement 1.

By letter dated May 29, 1990 (Reference a),

RG&E responded to NRC Bulletin 90-01 (Reference b).

Subsequently, NRC provided closeout of the original bulletin in a letter dated December 4,

1990 (Reference c).

NRC Bulletin 90-01, Supplement 1 provided information to update Bulletin 90-01 and requested licensees to review this information for applicability and modify, as appropriate, actions and enhanced surveillance programs as described in the supplement to the bulletin.

As stated in References (a) and (c),

RG&E did not need to develop an enhanced surveillance

program, because the requested actions of Bulletin 90-01 were determined not to be applicable.

RG&E has reviewed the information provided in Supplement 1 to the bulletin and we have determined that there is no need to replace or monitor using the enhanced surveillance monitoring program any of the Rosemount transmitters in service or in stock at Ginna Station.

This is based upon the fact that each of these transmitters falls into one of the categories that may be excluded

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from the enhanced surveillance program requested by Supplement 1.

A tabulation of the Rosemount transmitters in service or in stock and the basis for their exclusion from the enhanced surveillance program is included as Attachment 1.

All models of installed transmitters are used in Non-RPS/Non-ESF/Non-ATWS applications.

In addition, the only model 1153 transmitters manufactured before July 11, 1989 that are installed are used in Low Pressure applications (less than or equal to 500 psi).

Therefore, in accordance with the Reporting Requirements of Bulletin 90-01,. Supplement 1,

RG&E has complied with the actions requested.

Very ruly yours, x-C'obert C. Mecre y GAH4270 Subscribed and sworn to before on this 5th day of March, 1993

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Mr. Allen R. Johnson (Mail Stop 14D1)

Project Directorate I-3 Washington, D.C.

20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA.

19406 U.S.

NRC Ginna Senior Resident Inspector

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ATTACHMENT 1 Tabulation of Rosemount Transmitters Installed at Ginna Station Service Transmitter Safety Model Class*

Basis for Exclusion Steam generator wide range level 1154 SC-3 Note 1

Reactor coolant 1B 2

pump oil level Main Steam Flow Residual Heat removal pump suction pressure 1153 1152 1151 NNS SS SS Note 2

Note 3

Note 3

Catalytic oxygen Removal System (CORS) skid 1151 NNS Note 3

As defined in the Ginna Quality Assurance Manual:

SC-3 SS NNS is a

safety-related classification for equipment performing a safety class 3 function is a non-safety related classification for equipment performing a special (safety significant) function is a non-safety related classification for equipment not performing any safety-related or safety-significant functions.

Note 1:

Based upon the conclusion stated in paragraph 5.

(page 8

of Bulletin 90-01, Supplement

1) and Requested Action 1.

.(page 9), Rosemount transmitters model 1154,.manufactured after July 11, 1989 having a serial number greater than 500000 do not require follow up actions and are excluded from the enhanced surveillance program.

The steam generator wide range level transmitters were purchased in January 1991.

Serial numbers for the four installed transmitters and one spare are 0503367,

0503368, 0503369,

0503370, and 0503371.

Therefore, these transmitters are excluded.

Based upon the conclusion stated in paragraph 2.a.

(page 7 of Bulletin 90-01 Supplement 1) and Requested Action 1.f. (p. 11), Rosemount transmitters model 1153 that have a normal operating pressure less than or equal to 500 psi may be excluded.

In addition, these transmitters are non-safety related and are backed up by independent oil level float switches.

Based upon the conclusion stated in paragraph 6.

(page 8

of Bulletin 90-01, Supplement

1) and Requested Action 1.

(page. 9), Rosemount transmitter models 1151 and 1152 do not indicate the need for follow up action, because performance experience does not warrant additional licensee action.

In addition, these transmitters are non-safety related.

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