ML20044B869

From kanterella
Jump to navigation Jump to search
Responds to Suppl 1 to NRC Bulletin 90-001, Loss of Fill Oil in Transmitters Mfg by Rosemount. Util Will Replace 23 Unit 2 Rosemount Transmitters During Spring 1993 Unit 2 Refueling Outage
ML20044B869
Person / Time
Site: Calvert Cliffs  
Issue date: 03/04/1993
From: Denton R
BALTIMORE GAS & ELECTRIC CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
IEB-90-001, IEB-90-1, NUDOCS 9303110193
Download: ML20044B869 (4)


Text

e BALTIMORE GAS AND ELECTRIC

,%g 1650 CALVERT CUFFS PARKWAY LUSBY, MARYLAND 20657-4702 RostrtT E. DENTON VICE PRESIDENT NUCLEAR ENERGY (4tc) 260 4 455 e

hiarch 4,1993 U. S. Nuclear Regulatory Commission Washington,DC 20555 ATTENTION:

Document Control Desl:

SUBJECT:

Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2: Docket Nos. 50-317 & 50-318 Rerpcmse to NRC Bulletin No. 90-01, Supplement 1; less of Fill-Oil in Transmitters Manufactured by Rosemount

REFERENCES:

(a)

Letter from Mr. G. C. Creel (BG&E) to NRC Document Control Desk, dated July 17,1990, "NRC Bulletin No. 90-01: Loss of Fill-Oil in Transmitters Manufactured by Rosemount" (b)

Letter from Mr. G. C. Creel (BG&E) to NRC Document Control Desk, dated April 29,1992, " Supplemental Response to NRC Bulletin No. 90-01: Ioss of Fill-Oil in Transmitters Manufactured by Rosemount" (c)

Letter from Mr. W. H. Rasin (NUMARC) NUMARC Administrative Points-of-Contact, dated April 6,1990, "Rosemount Transmitter Oil Loss" (d)

Letter from Mr. G. C. Creel (BG&E) to NRC Document Control Desk, dated September 16, 1992,"1992 Refueling Outage; Summary of Completed Licensing Actions" Gentlemen:

NRC Bulletin No. 90-01, Supplement I requires each Operating Reactor Licensee to submit a response to the items included under " Reporting Requirements." Accordingly, Baltimarc Gas and Electric Company hereby provides the response in Enclosure (1).

g([

>p)0 Ind 110007 47 8

9303110193 930304 PDR ADOCK 05000317 i

O PDR

a

+

8 Document Control Desk March 4,1993 Page 2 Should you have any further questions regarding this matter, we will be pleased to discuss them with you.

Very truly yours, h A l\\

STATE OF MARYLAND :

TO WIT :

COUNTY OF CALVERT I hereby certify that on the hd day of JJ A/J

,1993, before me, the subscriber, a Notary Public of the State of Maryland in and for personally appeared Robert E. Denton, being duly sworn, and states that he is Vice President of the Baltimore Gas and Electric Company, a corporation of the State of Maryland; that he provides the foregoing response for the purposes therein set forth; that the statements made are true and correct to the best of his knowledge, information, and belief; and that he was authorized to provide the response on behalf of said Corporation.

WITNESS my Hand and Notarial Scal:

e Notary Public My Commission Expires:

.,_dediaAu /, /f7M V

f Dfte RED /TWG/twg/bjd/dlm

Enclosure:

(1)

BG&E Response to NRC Bulletin No. 90-01, Supplement 1 cc:

D. A. Brune, Esquire J. E. Silberg, Esquire R. A. Capra, NRC D. G. Mcdonald, Jr., NRC T. T. Martin, NRC P. R. Wilson, NRC R. I. McLean, DNR J. H. Walter, PSC

l s

ENCLOSURE 0) i

!!G&E RESPONSE TO NRC BULLETIN NO. 90 01, SUPPLEMENT 1 t

i HrrouTING REOUIREMENT 1 Will BG&E take the actions requested in Requested Actions for Operating Reactors?

J IIG&E Resiumse Baltimore Gas and Electric Company will complete all the actions requested in NRC Bulletin 904)1, Supplement 1 except Requested Action 2. Based on the response to Reporting Requirements 2.c i

and 3, an evaluat:on of the enhanced surveillance monitoring program (i.e., Requested Action 2) is not applicable to Calvert Cliffs Nuclear Power Plant Units 1 and 2.

t REronTING HEOUIREMENT 2.a Provide a list of specific actions BG&E will complete for the actions being taken to meet Item 1 of Requested Actions for Operating Reactors. Include justifications as appropriate.

ilG&E Restwmse Plant records have been reviewed and plant walkdowns have been performed. All Rosemount l

Model 1153 Series B,1153 Series D and Model 1154 pressure and differential pressure transmitters manufactured prior to July 11, 1989, that are used or may be used in the future in safety-related systems or systems installed in accordance with 10 CFR 50.62 (hereinafter referred to as Bulletin transmitters) have been identified. Reference (a) was our initial response to NRC Bulletin 90-01. It states that 31 Bulletin transmitters per unit were being used in safety-related systems and an additional 46 Bulletin transmitters were in stock for future use at Calvert Cliffs Nuclear Power Plant Units 1 and 2. Additionally, as stated in Reference (a), the scope of our replacement program was never limited to suspect lot transmitters. Our program requires replacing all Bulletin transmitters.

Subsequent to the submittal of Reference (a), we informed you in Reference (b) that we had revised i

the scope of Bulletin transmitters to be ccmsistent with Enclosure (1) of Reference (c). The scope has been narrowed to only those transmitters "which perform safety-related (or ATWS) functions" rather than those " utilized in safety.related systems." We hav: excluded Bulletin " transmitters whose only safety function is that of a pressure boundary." In addition to excluding pressure boundary only Bulletin transmitters, we have re-evaluated the safety related functions of other transmitters.

Reference (b) concluded that as a net effect we will replace 24 Unit 1 Rosemount transmitters, 23 Unit 2 Rosemount transmitters and 2 Rosemount transmitters common to both units.

Replacement in this context means that we will either replace the transmitters with transmitters which have been refurbished with a sensor module manufactured after July 11,1989, or replace the transmitters with transmitters manufactured after July 11,1989.

Enclosure (1) of Reference (d) provided notification that all Unit 1 Rosemount transmitters and all Rosemount transmitters common to both units were replaced as of August 31,1992. Replacement transmitters were manufactured after July 11,1989.

Based on the response to Reporting Requirements 2.c and 3, Items 1.e and 1.f of Requested Actions for Operating Reactors are not applicable to Calvert Cliffs Nuclear Power Plant Units 1 and 2.

I

_ -.. ~.

I ENCLOSURE (1) o~

IIG&E RESPONSE TO NRC llULLETIN NO. 90-01, SUPPLEMENT 1 RrrouTING REottinnts:NT 2.b Provide the schedule for completing the requested actions for the actions being taken to rncet item 1 of Requested Actions for Operating Reactors provided in this supplement.

ilG&E Restumse i

Baltimore Gas and Electric Company will replace the 23 Unit 2 Rosemount transmitters during the l

spring 1993 Unit 2 Refueling Outage.

REROUTING Hrovinnti:NT 2.c Regarding the requested actions that BG&E is taking, provide a statement confirming that Item 2 of Requested Actions for Operating Reactors has been completed.

IIG&E Restwmse Baltimore Gas and Electric Company is not implementing an enhanced surveillance monitoring l

program for Bulletin transmitters, therefore we are not completing item 2 of Requested Actions for Operating Reactors.

5 REroRTING N00titHDti:NT3 Provide a statement identifying those actions requested by the NRC that BG&E is not taking and an

[

evaluation which provides the bases for not taking the requested actions.

IlG&E Resiumse Baltimore Gas and Elcetric Company is not completing Requested Action 2. We have chosen the option to replace Bulletin transmitters rather than the option to implerr ent an enhanced surveillance monitoring program. Therefore, item 2 of Requested Actions for Operating Reactors is not applicable to Calvert Cliffs Nuclear Power Plant Units 1 and 2.

i 2

l