ML18219D922

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Letter Stress Corrosion Cracks in Stagnant, Low Pressure Stainless Piping Containing Boric Acid Solution at PWRs
ML18219D922
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 04/15/1977
From: Dolan J
American Electric Power Service Corp
To: James Keppler
NRC/IE, NRC/RGN-III
References
Download: ML18219D922 (5)


Text

AMERICAN ELECTRIC POWER Service Corporation 2 Broadtttay, Nettt York, N. Y. 10004 (212) 422.4800 JOHN E DOLAN Senior EttecutioeVice Preeittent Engineering 4 Conetrttction April'15, 1977 Donald C. Cook Nuclear Plant Unit No.

1 Docket No. 50-315 DPR No.

58 Mr. J.

G. Keppler, Regional Director U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region IXX 799 Roosevelt Road Glen Ellyn, Xllinois 60137

Dear Mr. Keppler:

Xn our December 29, 1976 letter we responded to your letter-of November 26, 1976 addressing IE Circular No. 76-06

entitled, "Stress Corrosion Cracks in Stagnant, Low pressure Stainless piping Containing Boric Acid Solution at PWR's."

In that response we stated that we have been working.on a program which:

(a) defines those portions of safety-related piping systems which come under the criteria of not being frequently flushed,.or containing non-flowing liquids; (b) considers hydro-static testing for safety related piping; (c) attempts to define the appropriate non-destructive examination techniques; and (d)= develops a schedule 'for the inspections which can 'be made at the Donald C.

Cook Nuclear Plant Unit 1.

This letter is intended to provide the information requested by your November 26, 1976 letter and to supplement our December 29, 1976 letter.

aI a21 1977

0

The portions of safety-related piping systems 'in the Cook Nuclear Plant containing Boric Acid solution which come under the criteria of not. heing frequently flushed, or containing non-flowing liquids are:

1)

Accumulator to Reactor Coolant System Cold Leg.

2)

Boron Injection Tank to Reactor Coolant System.

3)

Refueling Water Storage Tank to CVCS.

4)

RHR Valves-ICM 305 S 306 to Pumps'.

5)

RHR Pump Suction to Containment Spray Pump Suction.

6)

Spray Additive Tank to Containment Sprays.

7)

Crosstie Safety Injection to CVCS.

8)

Crosstie RHR to CVCS.

9)

RHR to Containment SPrays Valves IMO 330

& 331.

10)

Safety Injection to Reactor Coolant System Cold:Leg.

ll)

Safety Injection to Reactor Coolant System Hot Leg.

12)

RHR to Reactor Coolant System Cold Leg.

13)

RHR to Reactor Coolant System Hot Leg.

14)

Blender Makeup to Refueling Water Storage Tank (RWST).

15)

Refueling Water Storage Tan'k to Purification Pump.

16)

Purification Filter to RWST.

17)

ECCS Check Valve 'Leakage Testing Lines.

18)

RHR return to RWST.

19) 'rosstie RHR to SI.

Mr. J.

G. Keppler Apri 15, 1977 In response to item 01. of IE Circular No. 76-06. an operational pressure leakage test willbe performed in accordance with ASME Code Section XX rules 1974 edition through summer 1975 addenda, except that the test pressure willbe at system operating pressure.

This test willbe done on -as many of the above 19 portions of safety-related piping systems

'as is possible during the next scheduled shutdown in late summer 1977. If there are any remaining portions to be tested they willbe done during the next scheduled shutdown for refueling.

A review of the above 19 portions of safety-related piping systems has shown that these portions. of piping systems willbe part of our revised program for performing ASME Section XI Inservice Xnspection of ASME Section IXI Class 2s3 components and systems and will be examined during those inspections.

In

-the interim we will continue the surveillance requirements of the Donald C. Cook Nuclear Plant Technical Specifications regarding leak detection and operability of safety-related equipment together with our response to FSAR Question 6.6 regarding in-service inspection of other fluid systems.

This program of operational pressure leak testing and inspections together with the Cook Nuclear Plant Technical Specification surveillance requirements and the ASME Section XI Inservice Inspection program provide substantial assurance of the integrity of the portions of safety-related piping systems containing Boric Acid solution which are not frequently flushed.

Very truly yours; JED:mam ohn E. Dolan Senior Executive Vice President Engineering and Construction cc:

Gerald Charnoff R. C. Callen P.

W. Steketee R. Nalsh R. J. Vollen R. S. Hunter R.

W. Jurgensen Bridgman Dr. Ernst Volgenau, Director Office of Xnspection and Enforcement

E I