ML17146B055

From kanterella
Jump to navigation Jump to search
Summary of 871105 Meeting W/Util in Bethesda,Md Re Exemption from GDC-4 for Potential Deficiency in Jet Impingement Analysis
ML17146B055
Person / Time
Site: Susquehanna 
Issue date: 12/04/1987
From: Thadani M
Office of Nuclear Reactor Regulation
To: Butler W
Office of Nuclear Reactor Regulation
References
NUDOCS 8712080424
Download: ML17146B055 (5)


Text

, ~

>. ~I>R RE(>y

~4, P0 Cy

(>

C O

((

O~

+~

~O

+i*++

MEMORANDUM FOR:

FROM:

SUBJECT:

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 December 4( l987 Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II'ohan C. Thadani, Project Manager Project Directorate I-2 Division of Reactor Projects I/II MEETING WITH PENNSYLVANIA POWER AND LIGHT COMPANY REGARDING EXEMPTION FROM GDC-4 FOR POTENTIAL DEFICIENCY IN JET IMPINGEMENT ANALYSIS On November 5, 1987, at the request of Pennsylvania Power and Light Company (the licensee for Susquehanna Steam Electric Station),

a meetinq was arranged with the Materials Engineering Branch Staff (K. Wichman, Samson Lee and Bill Koo), Mechanical Engineering Branch staff (S.

Hou and A. Lee), Project Direc-torate I-2 (W. Butler and M. Thadani),

and the licensee and its contractor.

Enclosure 1 is a copy of the meeting notice.

Enclosure 2 is a list of meeting attendees.

The purpose of the meeting was to provide clarification to the licensee for the staff's request for additional information, dated September 28, 1987.

The staff's request was based on questions raised by the Materials Engineering Branch related to the licensee's request for exemption from certain requirements of GDC-4.

The licensee stated that the objective of the analysis supporting its Octo-ber 17, 1986 request was to get exemption from the of GDC-4 requirements to shield the MSIVayerators aoainst the calculated loads due to jet impingement resulting from pipe cracks at the reactor pressure vessel nozzle pipe-to-safe end weld.

The leak-.before-break analysis was used to demonstrate unlikelihood of breaks at the specific locations not being detected in time to take cor-rective action.

The licensee had no intention of seeking exemption from all aspects of the GDC-4.

The licensee felt that the staff's questions were more in line with the GDC-4 exemptions to permit removing pipe restraints.

The Materials Engineering (EMTB) Staff agreed that these questions were strictly directed to the leak-before-break-

analysis, did not go into the exemption from MSIV protection against jet impingement required by the GDC-4 and need not be answered in the present form.

The Mechanical Engineering Branch (EMEB) staff indicated that they were not consulted by the EMTB staff on the SSES exemption request but will discuss the request with their Branch Chief and define their review scope.

The EMEB review will probably be specific to the required exemption and wi 11 depend upon the EMTB review of the leak-before-break analysis.

The EMEB staff proposed that the licensee should consider the Sandia National Laboratories jet model which is more realistic and is acceptable to the staff.

The staff felt that the Sandia model may show that the calculated jet loads may be smal'Ier and the problem may not be as serious as thought by the licensee.

8712080424 8712'04 PDR

'ADQCII'5000387 P

PDR

(

At the end of the meeting the NRC Project Manager requested that the licensee should respond to the NRC request for additional information in the light of the current understanding of the issues involved without answering all the leak-before-break questions sent to the licensee.

/s/

Mohan C. Thadani, Project Manager Project Directorate I-2 Division of Reactor Projects I/II

Enclosures:

Meeting Notice Meeting Attendees DISTRIBUTION NRC PDR Local PDR PDI-2 Reading WButler MThadani/DFischer OGC-Bethesda EJordan JPartlow,;

NRC Partscipants ACRS (IO)

HBC1 P

MThandani:cp

/~ /9 /87 PDI-2/D WButler t>/~/87 C.

Y. Cheng L. B. Marsh K. Wichman S.

Lee W.

Koo S.

Mou A. Lee

.r k

At the end of the meeting the NRC Project Manager requested that the licensee should respond to the NRC request for additional information in the light of the current understanding of the issues involved without answering all the leak-before-break questions sent to the licensee.

Mohan C. Thadani, Project Manager Project Directorate I-P Division of Reactor Projects I/II

Enclosures:

Meeting Notice Meeting Attendees