ML19262A281
| ML19262A281 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/03/1975 |
| From: | Arnold R METROPOLITAN EDISON CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| GQL-3363, NUDOCS 7910260611 | |
| Download: ML19262A281 (3) | |
Text
NRC DISTRIBUTION FOR PART 50 DOCKET MATERI AL
- (TEMPORARY FORM) 4, 107G4 CONTROL NO:
FILE:
FROM: Met. Edison Company DATE OF DOC D ATE R EC'D LTR TWX RPT OTHER Recding, Pa.
19603 pf 36m1s 10-3-75 10-2-75 XX TO:
ORIG CC OTHER SENT NRC PDR XX NRC 3 signed 37 SENT LOCAL PDR XX CLASS UNCLASS PROPINFO INPUT NO CYS REC'D DOCKET NO:
XXX 40 50-289 DESCRIPTION:
Ltr re our 5-27-75 & 8-22-75 ENCLOSURES: Rockwell Reports :
ltrs....furn addl info on Main Steam Isolation (1) 2573-51 entitled Energy Absorption in the Valves & trans the followin3:
Size 24 Fig. 607 Valve Seat & Distk....
(2) 2573-49 entitled Disk Velocity at Impact with Seat for Line Break at Upstream Side of Size 24 Fig. 607-Non-Return Valve...
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1975 *. ~ 0 Director of Nuclear Reactor Regulation g[-
U. S. Nuclear Regulatory Commission
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'v' Washington, D. C.
20555 W;
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Dear Sir:
' F3 -
Three Mile Island Nuclear Station Unit I (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 This letter is in response to your letter of May 27, 1975 and our letter of August 22, 1975 regarding your request for additional in-formation on our Main Steam Isolation Valves (MSIV's).
As stated in our previous correspondence the MSIV's installed at IMI-1 can withstand a sudden closure which would result from an in-stantaneous release of pressure upstream of the valves. This statement is supported by the attached Rockwell reports, 2573-49 and 2573-51.
In addition, responses to your specific questions are provided as follows:
NRC QUESTION 1.
Provide a summary of the analynes employed to confirm
~'
the integrity of the main steam isolation valves (MSIVs) under the dynamic loads associated with the postulated steam line breaks. Include the following:
' T, (a) The maximum calculated impact energy that will be sustained by valve internal elements and seating surfaces under the conditions imposed by postulated main steam line breaks for your station. For Y-pattern h
globe MSIVs, this response should address both forward and reverse flow.
Response to Item (a) The maximum calculated impact energy that will be substained by valve internal elements etc.: Page 2 of Report 2573-51; impact energy =1,380,000 in. Ib. with a disk velocity of 107 f t/sec.
W 1484 324
/
- (b) A summary of the methods employed to calculate the energy levels given in response to (a) above.
Response to Item (b)
This is covered in Rockwell Report 2573-49.
(c) A summary of the maximum stress or strain calculated to occur in the principle elements of the valve assembly when subject to the impact forces characterized in (a) above.
Response to Item (c) A summary of the maximum stress or strain.
The maximum stress occurs below the seat and is calculated at 46.2 ksi (Page 3 of Report 2573-51).
(d) A summary of any other methods or criteria employed in conjunction with, or in lieu of, the information requested in (a), (b), and (c) above to provide assurance that the valve is adequately designed to perform the specified safety functions.
Response to Item (d)
This has been defined in Report 2573-51.
NRC QUESTION 2.
Describe any modifications incorporated in, or to be incorporated in, the main steam isolation valves at your station. Provide the present schedule for completion of this work.
Response to Question 2 - No modifications have been made nor will any be required.
3 We trust that this submittal adequately resolves any concerwyou have and should you have any questions, please contact me.
Sincerely,
/G?
/]
NOLD Vice-Pres ident RCA:CWS:rk File: 20.1.1/7.7.3.1.1 Attached:
Rockwell Reports #2573-51 & 2573-49 1484 325