ML19309B746

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Responds to NRC Ltr Re Violations Noted in IE Insp Rept 50-341/79-24.Corrective Actions to Be Reported in Detail to NRC Inspectors on Next Visit.Discussion of Infraction Encl
ML19309B746
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 01/31/1980
From: Hines E
DETROIT EDISON CO.
To: Fiorelli G
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19309B743 List:
References
EF2-47-357, NUDOCS 8004070135
Download: ML19309B746 (4)


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Edward Hines Anset wc Pmsorm ouaa, a. sam v

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Edison

=3H W BgBeav~ Rrad w-January 31, 1980 EF2-47,357 Mr. G. Fiorelli, Chief Reactor Construction and Engineering Support Branch U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137

Subject:

Non-Compliance at Enrico Fermi Unit II Construction Site

Dear Mr. Fiorelli:

This letter respond; to the infraction contained in your IE Report 50-341/79-24.

This inspection of Enrico Fermi Unit II Site Construction activities was performed by Messrs. F. J. Jablonski and J. Hughes on November 27-29, 1979.

Only the cited infraction mentioned in your report is discussed in this reply, as required by Section 2.201 of the NRC's " Rules of Practice", Part 2, Title 10, Code of Federal Regulations.

The un-resolved items are being acted upon. We will be prepared to re-port in detail on our progress and corrective action on this matter to your inspectors on their next visit.

i The enclosed response is arranged to the sequence of items cited in the body of your report.

The finding and section numbers are referenced.

We trust this letter satisfactorily answers the concerns raised in your report. We shall be glad to discuss any further concerns you may have.

Sincerely yours, W%

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.O EH/ RAW /lm Enclosure cc:

Mr. John G. Davis Acting Director Office of Inspection and Enforcement Division of Reactor Inspection Programs

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kh lOkhb U.S. Nuclear Regulatory Commission Washington D.C.

20555 806.4070 l %

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2 THE DETROIT EDISON COMPANY QUALITY ASSURANCE DEPARTMENT-ENRICO FERMI 2 PROJECT Response to NRC Report No. 50-341/79-24 Docket No.-50-341 License No-. CPPR-87' Inspection at: Fermi II Site, Monroe, Michigan

. Inspection conducted: November 27-29, 1979 4_

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' Prepared by:

H. A. Walker

' Site Project QA Engineer Approved by:

R. W. Barr i

Project QA Director Detroit Edison Company I:

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b Response to NRC' Report #50-341/79-24

-Statement'of' Infraction 79-24,' Appendix A Infraction: Contrary to 10CFR50, Appendix B, Criterion'III; Enrico Fermi 2 QA Manual, QAP No. 3 subparagraph'3.1.3.3; and 10CFR50, Appendix A, Criterion IV, "the licensee failed to review the suitability of stem mounted limit switches located on the Main Steam Isolation Valves (MSIV).

The switches are used to provide operator information read-out and initiate protective action signals."

Corrective Action Taken and Results Achieved The: main steam isolation valve limit switches provide two basic functions :

1) Control room indication of the valve position, and
2) Sensing logic for an anticipatory scram of the reactor when three of the four steam lines are closed.

A post-LOCA environmental qualification of these switches is not required since the position indication is not a safety function and the reactor trip input is not required to function subsequent to a LOCA event.

In the case of a LOCA, the MSIV closure would not be the primary scram input since reactor level and/or drywell pressure would precede the actua1' isolation valve closure signals.

In addition, a complete failure of the MSIV limit switches following a spurious MSIV closure would not result in overpressure and/or fuel damage

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due to the timely operation of the flux or pressure scrams. This analysis is contained in Appendix 5A of the FSAR.

General Electric has verified that the switch qualification exceeds that expected during normal operation; the junction box and hookup wire furnishe'd with the MSIV's have been tested for the following steam environment profile:

First 3 hrs.

103 psig & 340 F Next 3 hrs.

75 psig & 320 F Next 16 hrs.

16 psig & 250 F It was found that the switch functioned normally at the beginning, during and the end of each test period.

Corrective Action to be Taken to Avoid Further Non-Compliance Vendor Document. Packages (VDP's) are prepared for safety related systems.

As a part of a VDP,.all the components performing safety funccions are l

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rsponse:to NRC' Report #50-341/79-24 Page Two

i Corrective Action to be Taken to Avoid Further Non-Compliance (cont'd) identified and adequacy of environmental qualification documentation as applicable.for these components is verified. This-is properly _ recorded in the VDP by indicating storage location and file number of the documents

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for easy retrieval.

We have followed the-policy of qualifying our electrical' equipment to

. the standard in~effect_at the' time of purchase.

Regulatory Guide 1.89 mentioned in the IE Circular 78-08 applies in its implementation section only to equipment purchased after November 15, 1974. Fermi 2 has followed this requirement for all:new purcahse orders dated November 15, 1974, or later. However, as equipment deficiencies or failure modes come to light, studies are initiated to evaluate their impact on Fermi 2 installation.

Corrective action is then taken if required.

Date When Full Compliance Will be Achieved It is Detroit Edison's position that the Fermi 2 Project is within full compliance on the requirements for the subject limit switches.

Documentation for safety-related equipment furnished by the NSSS supplier, General Electric, is maintained at their facilities and verified by-Edison by audit.

The Main Steam Isolation Valves are part of the General Electric supply.

Items identified in FSAR section 3.11 and supplied by-General Electric will be audited by March 30, 1980. We will advise you of the audit dates when arrangements have been finalized, l

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