ML20100B562

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Responds to NRC Re Areas of Concern Noted in Insp Rept 50-247/84-34.Corrective Actions:Method of Collecting, Maintaining & Retrieving Records Re Auxiliary Feedwater Regulating Valves Implemented
ML20100B562
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 03/15/1985
From: Otoole J
CONSOLIDATED EDISON CO. OF NEW YORK, INC.
To: Starostecki R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 8503280442
Download: ML20100B562 (3)


Text

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John D. o'Toole Vce President l.

Consolidated Edison Company of New York, Inc.

4 trying Place, New York, NY 10003 Telephme (212) 460-2533 March 15, 1985 Re:

Indian Point Unit No. 2 Docket No. 50-247 Richard W. Starostecki Director Division of Reactor Projects Region 1 U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406

Dear Mr. Starostecki:

This refers to I.E. Inspection 50-247/84-34 conducted by Mr.

T. Kenny of your office on December 10-19 and 22, 1984 of activities authorized by NRC License No. DPR-26 at Indian Point Unit No. 2.

Your February 6, 1985 letter set forth certain areas of concern as a result of this inspection.

Provided herewith as Attachment A is our response to these concerne.

Should you or your staff have any questions, please contact us.

Ve truly yours,

/

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l Attachment cc Senior Resident Inspector l

U.S. Nuclear Regulatory Commission P.O. Box 38 l

l Buchanan, New York 19511 l

i 8503200442 850315 ADOCK0500g7 DR e

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l ATTACBNENT A RESPONSE TQ ITEMS QE CONCEBE ITEM 1.

The 354 setting referred to in one of the licensee submittals does not have a basis and does not delineate if the setting is the valve or the. controller.

RESPONSE

1The auxiliary feedwater regulating valves were originally constructed and maintained as a non-class A system (i.e.

non-safety related).

The testing and records keeping 1 requirements were therefore not as stringent as for class A systems.

As stated in in Abnormal Operating. Procedure A-1 rev. 3, the 354 setting was intended to correlate with a flow rate of 150 gpm to each steam generator, thus satisfying the FSAR Accident Analysis for the loss of normal feedwater and provides an~ initial auxiliary feedwater flow rate which

. minimizes ~the risk of water hammer.

This same procedure describes the 35 percent setting as narcant valve gggD.

1.

Based on.a flow test. conducted on December 22, 1984, the

' auxiliary'feedwater regulating valves have been set to deliver a minimum initial flow of 158 gpm to each steam generator.

ITEM 2 The curve relating to flow through the feedwater regulating valves that existed prior to the one recently acquired from the valve manufacturer was not an authorized curve and apparently had not been approved by engineering.

RESPONSE

The first curve referred to was a generalized curve prepared

.in 1983 to show a method of calculating a valve setting for a specified flow:and pressure drop, based on any given valve flow characteristics.

The recently received manufacturer's curve, dated November 5, 1984, shows the design characteristics of the trim purchased for the modification made in 1981.

However, the trim then received was not the same as that which was ordered, and required on-site re-machining to meet the full flow requirements as analyzed for safety.

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ITEM 3 As delineated in Report 84-21, the record storage system is inadequate to retrieve records in a reasonable amount of time. In fact, during the course of this inspection, certain records could not be found.

RESPONSE

As discussed in our response to NRC inspection report 50-247/84-21, an improved method of collecting, maintaining and retrieving records will be implemented.

This method will provide for accurate retrieval of records without undue delay.

ITEM 4.

No records could be produced that confirmed that the trim installed in the valves presently is the same as the trim that was in the original.

RESPONSE

The trim presently installed in the valves is not the same as in the original valves, as they were modified in 1981 to improve controlability and prevent cavitation damage.

l Records documenting the installation of the present trim l

along with the corresponding safety evaluation are available for review by the resident inspector.

l As mentioned in response to Item 1, the auxiliary feedwater l

regulating valves were originally constructed and maintained as a non-class A system; the testing and records keeping requirements were not as stringent as for class A systems.

The improved method of collecting, maintaining and retrieving records mentioned in response to Item 3 will provide for accurate retrieval of records without undue delay.

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