ML18031A031

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Summarizes Results of 781019 Meeting Between NRC & Mark II Owners.Substantial Progress Was Made Re Pool Dynamics for Lead Mark II Plants & Allocation of Staff Tech Resources for Review of Generic Mark II Intermediate Prog
ML18031A031
Person / Time
Site: Susquehanna  Talen Energy icon.png
Issue date: 11/20/1978
From: Boyd R
Office of Nuclear Reactor Regulation
To: Curtis N
PENNSYLVANIA POWER & LIGHT CO.
References
NUDOCS 7811290371
Download: ML18031A031 (6)


Text

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Docket No.

50-387 and 50-38 UiJITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 NOV 30 iS78 Mr.

Norman W.

Cur tis Vice President - Engineering and'onstruction Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Gentlemen:

SUBJECT:

MARK II GENERIC ACCEPTANCE CRITERIA FOR LEAD PLANTS-Substantial progress was made at our meeting of October 19, 1978, with the Mark II owners toward resolution of the issues related to pool dynamics for the lead Mark II plants and allocation of staff technical resources for review of the generic Mark II Intermediate Program.

The purpose of this letter is to summarize the meeting results and to state our intent on future efforts leading to the completion of staff review of these matters.

The most significant developments relate to the method of combining loads and acceptability of the pool dynamics load criteria as discussed below:

The staff believes that further extension of the approval for SRSS methods to include combining SRV and OBE loads appears possible and certainly worth the investment of staff and applicant resources to review and develop a technically justi-fiable basis for licensing.

We anticipate completion of our review of this matter before the end of the year, at which time we will specify conditions for the use of SRSS in the Mark II program.

The Mark II owners agreed to adopt the NRC lead plant pool dynamic load acceptance criteria with a limited number of exceptions.

This agreement, in several

cases, was based on favorable consideration of SRSS methods by the staff.

The exceptions and the program to resolve the exceptions on a

generic basis are described in Enclosure 1.

Resolution of these exceptions to the NRC criteria is to be accomplished before the end of 1978.

The Mark II owners identified the Intermediate Program tasks where a priority review by the staff is needed.

The staff agreed to schedule a November meeting to discuss staff concerns related to those tasks where sufficient information has been submitted to warrant 'a meeting (see enclosure 2).

While this course of action will help to maintain the near term licensing schedules for the lead plants, resolution of those exceptions taken by the Mark II owners to the staff generic acceptance criteria would require a substantial portion of the staff's resources.

As a result, we antici-pate some delay in our overall review of the Intermediate Program Tasks through the end of 1978.

In recent weeks we have received several requests for plant-unique review of tasks already included in the Mark II owner's Intermediate Program.

We will not give as high priority to such meetings as we do to generic program meetings.

Recognizing the limitations on staff resources, we reiterate the need for the Mark II owners to utilize the generic Intermediate Program to the maximum extent possible.

The generic approach to resolution of the pool dynamics issues provides the greatest potential for completing the licensing activities in a timely manner for the plants utilizing Mark II containments.

Sincerely,

(

,C Roger S.

Boy<I, Director Division of Project Management Office of Nuclear Reactor Regulation

Enclosures:

. 1.

Exceptions to the NRC Mark II Pool Dynamic Load Acceptance Criteria 2.

Priority Intermediate Progr am Tasks cc:

See next page

Hr. Norman W..Curtis cc:

Hr. Earle M. He'ad Project Manager Pennsylvania Power 5 Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Jay Si lberg, Esq.

Shaw, Pittman, Potts 5

Trowbridge 1800 M Street, N.

W.

Washington, D. C.

20036 Hr. William E. Barberich, Nuclear Licensing Group Supervisor Pennsylvania Power

& Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Edward M. Nagel, Esquire General Counsel and Secretary Pennsylvania Power 8 Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Bryan Snapp, Esq.

Pennsylvania Power 5 Light Company 901 Hamilton Street Allentown, Pennsylvania 18101 Robert H. Gallo Resident Inspector P. 0.

Box 52 Shickshinny, Pennsylvania 18655

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Enclosure 1

Exceptions to NRC Mark II Pool Dynamic Load Acceptance Criteria 1.

Pool Swell Elevation I.B.l.b

  • The staff will identify before October 30, 1978 additional information to be provided by the Mark II owners to support their new methodology described in response to guestion 020.68.

The Mark II owners will provide a schedule for responding to the NRC's information request.

2.

Small Structure Im act Loads I.B.3.a The Mark II owners will notify the staff of a time when they will be ready to discuss and justify their revised methodology.

3.

As mmetric Pool Swell Loads I.B.5 The Mark II owners will send a letter report to the staff including the description and justification of a more realistic methodology for this load than the bounding methodology described in the NRC acceptance criteria.

4.

SRV Bubble Phasin II.B.b The owners. of the lead Mark II plants will propose a time when they will be ready to discuss and justify a generic methodology for establishing bubble phasing for the "T" quencher discharge device.

Boyd to lead Hark II plants.

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5.

SRV Bubble Fre uenc II.B.c The owners of the lead Mark II plants will propose a time when they will be ready to discuss and justify a new methodology for defining bubble frequency.'.

LOCA/SRV Submer ed Dra Loads III The staff will notify the Mark II owners of an acceptable meeting time with our consultants to discuss the Mark II owners revised methodology.

Emphasis will be placed on items III.A.l and III.A.2 related to the LOCA jet drag load and the "T" quencher zone of influence.

7.

Submer ed Boundar Load Durin Vent Clearin I.A The Hark II owners will send a letter report to the NRC clarifying the application of this load to the containment walls.

Reference will be made to observed loads on the walls of the 4T facility.

Enclosure 2

Priority Intermediate Program Tasks

  • 1.

Dynamic Single and Multi-Vent Lateral Loads

    • 2 Submerged Structure Ring Vortex Model
    • 3.

"T" quencher Submerged Structure Loads

    • 4.

"T" quencher Air Clearing Loads

  • 5.

Refined Chugging Loads

    • 6.

"T" and Four-Arm quencher Temperature Limit

    • 7.

New Four-Arm quencher Load Methodology

  • The staff is scheduling a meeting for November 1978 to discuss concerns associated, with our review of these items
    • The staff has not received sufficient documentation relating to these tasks to initiate a review.