ML20054K343

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Revises 820527 Response to NRC 820129 & 0222 Ltrs Re Deviation Noted in IE Insp Rept 50-302/81-23.Calibr Procedure Revised by Reinserting Omitted Data Sheet
ML20054K343
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 06/11/1982
From: Mardis D
FLORIDA POWER CORP.
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20054K339 List:
References
3F-0682-15, 3F-682-15, NUDOCS 8207010445
Download: ML20054K343 (3)


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June 11, 1982

  1. 3F-0682-15 File: 3-0-3-a-2 WPN2114 Mr. J. P. O'Reilly, Regional Administrator Office of Inspection and Enforcement U.S. Nuclear Regulatory Contaission 101 Marietta Street N.W., Suite 3100 Atlanta, GA 30303

Subject:

Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 IE Inspection Report No. 81-23

Dear Mr. O'Reilly:

Florida Power Corporation offers the following revised response to the Notice of Deviation cited in the subject inspection report. This letter supersedes our response contained in our letter dated May 28, 1982.

NOTICE OF DEVIATION Final Safety Analysis Report (FSAR) Section 7.1.2.2.3 specifies that the total worst case error produced in the reactor outlet temperature trip channel, which includes sensor, processing equipment and trip bistable errors, will not exceed i 1.0 F.

Contrary to the above, the procedure used to calibrate the reactor out-let temperature trip channel allows acceptance of a total error of i 3.066*F. This total includes a sensor error of t 0.065 F, a process error of i 2.5 F, and a bistable error of ! 0.5*F. In addition, the 13.065 F does not include the readability error of the signal converter meter used to calibrate the process equipment.

Response

Af ter this item was brought to the attention of Florida Power Corpora-tion, a thorough investigation was conducted. The deviation occurred because a data sheet had been inadvertently deleted from SP-112 during a previous revision. An interim change was made to the procedure reinserting the required data sheet. The omitted data sheet made it appear that only the signal meter was being utilized to check the signal 8207010445 820618 PDR ADOCK 05000302 G PDR General Office 3201 inirty fourtn street sou:n . P O Bou 14042. St Petersburg. Florida 33733 813--866 5151

Mr. J. P. O'Reilly U.S. Nuclear Regulatory Commission June 11, 1982 Page 2 converter output. This could have resulted in a process error of i 2.5*F as stated in the finding. Reinserting the subject data sheet specifies the use of a digital volt meter and limits the pro _ cess error to be 1 0.5 F. The total error is then as follows: RTD (i 0.065 F),

signal converter (i 0.5 F), and bistable (i 0.5 F). This could result in a worst case error of i 1.065 F in lieu of 21.00"F (as specified in the FSAR). However, the CR-3 Th bistable is set at 617.3 F t 0.5 F versus the Technical Specification limit of 618 F, which provides for an additional worst case conservative margin of 0.135 F.

Should there be any further questions, please contact this office.

Very truly yours, SwY 0 &

David G. Mardis Acting Manager Nuclear Licensing Hardis(F04)C5-2 cc: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555 i i

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STATE OF FLORIDA COUNTY OF PINELLAS David G. Hardis states that he is the Acting Manager, Nuclear Licensing of Florida Power Corporation; that he is authorized on the part of said company to sign and file with the Nuclear Regulatory Commission the information attached hereto; and that all such statements made and matters set forth therein are true and correct to the best of his knowledge, information and belief.

David G. Mardis b

Subscribed and sworn to before me, a Notary Public in and for the State and County above named, this lith day of June,1982.

%urGCG F Notary Public I

i Notary Public, State of Florida at Large, My Commission Expires: May 29, 1984 i

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