ML20034F730

Partially Deleted Ltr Discussing Recipient Concerns of Safety at Facilities,Including SPDS & Crack in Steam Generator.Actions Initiated to Examine Concerns

ML20034F730
Person / Time
Site:	Millstone
Issue date:	09/05/1990
From:	Haverkamp D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	AFFILIATION NOT ASSIGNED
Shared Package
ML20034F671	List: A09447, Informs That Util Completed Review of Identified Issue Re Activities at Unit 2.No Operability,Procedural or Valve Control Problem Associated w/RM-8123A/B.W/partially Deleted Encl A09448, Informs That Util Completed Review of Identified Issue Re Activities at Facility (RI-91-A-0034).Work Order Issued on 901205 to Fabricate Three Spare Svc Water Strainer Backwash Lines A09449, Submits Results of Review of Identified Issues Re Activities at Unit 2.Related Info Encl B13883, Partially Deleted Ltr Providing Addl Info Re Seismic Qualification of RCS Flow Transmitters Noted in Allegation RI-91-A-187 ML20034F670 ML20034F680 ML20034F681 ML20034F683 ML20034F708 ML20034F710 ML20034F714 ML20034F718 ML20034F724 ML20034F730 ML20034F738 ML20034F743 ML20034F754 ML20034F756 ML20034F761
References
FOIA-92-162 NUDOCS 9303040204
Download: ML20034F730 (1)

Text

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UNITED STATES

[

S NUCLEAR REGULATORY COMMISSION L

REGION I h

47s ALLENDALE ROAD K!NO OF PRUSSIA. PENNSYLVANIA 18408 SEP 0S1999 Docket No. 50-245 File No. RI-90-A-0116

SUBJECT:

Concerns you raised to the NRC regarding the Millstone Nuclear Power Station j

This refers to your conversation with Mr. Jeffrey Teator, on June i

20, 1990, in which you expressed additional safety concerns.

Specifically you identified the following concerns:

Nothing was done to address 1988 FWCI SSFI Dbservation Numbers 1-85-88 i

and 1-86-88 Category C, which may be the same problems that trade the l

licensee declare FWCI inoperable.

The Millstone Unit 1 Safety Parameter Display System (SPDS due to invalid data in the current system, because emergenc)y operating is inoperable procedures were revised.

P Millstone Unit 2 has cracks in the steam generator.

t i

We have initiated actions to examine your concerns as characterized above and will inform you of our findings.

i Should you have any additional questions, or if I can be of further assistance in this matter, please call me collect at (215) 337-5120.

4 k h w !* -

Donald R. Haverkamp, hief.

Reactor Projects Section 4A Division of Reactor Projects bec.

M. Perkins, DRMA A. Vegel, DRP i

W. Raymona, SFI, Millstone

}

Allegation File RI-90-A-0116 In!:rmation in this record as deMed in at;;rtan:: with the Freg9 CI Inl'"N!iUU Act, cr.e tiens d2 93o3o402o4 varios fMA -

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PDR FOIA HUBBARD92-162 PDR

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