ML17251A973

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Summarizes 880303 Discussions Re Facility Steam Generator Snubber Replacement Program & Plans to Replace Snubbers W/Rigid Structured Numbers.Completion of Technical Review Requested by 880406
ML17251A973
Person / Time
Site: Ginna 
Issue date: 03/04/1988
From: Wessman R
Office of Nuclear Reactor Regulation
To: Marsh L
Office of Nuclear Reactor Regulation
References
NUDOCS 8803100092
Download: ML17251A973 (4)


Text

4.

Docket 50-244 MEMORANDUM TO:

FROM:

SUBJECT:

Ledyard B. Marsh, Chief Mechanical Engineering Branch Division of Engineering and Systems Technology R.

H. Wessman, Director Project Directorate 1-3 Division of Reactor Projects I/II GINNA STEAM GENERATOR SNUBBER REPLACEMENT PROGRAM Per our discussion on March 3rd we agreed to the following:

(1)

Your staff will provide the P.M. within 30 days (April 6th) any additional requests for information that is needed to complete your review.

We will promptly transmit your information needs to RATE.

(2)

The licensee will be requested to submit all of the information as an amendment to the license.

This submittal is expected to include the necessary information on the effects of cold shutdown on the integrity of the steam generator system and associated piping and supports with the mechanical restrainsts.

(3)

Every effort will be made to complete the technical review and provide your SER within a 90 day period from the receipt of the licensee amendment package.

I trust that this is in accordance with our disscussion.

Original signed by:

R.

H. Wessman, Director Project Directorate 1-3 Division of Reactor Projects I/II 8803l0009'2 880304 PDR ADOCK 05000244 p

PDR As you are aware, the staff has.been reviewing RGItE plans to replace the Ginna steam generator snubbers with rigid structured members (bumpers).

The licensee had originally expected to make this modification under the provisions of 10 CFR 50.59.

Shortly before their February outage it became clear that a license amendment would be required and that several technical questions were not fully resolved.

The licensee did not proceed during the February outage with the replacement of hydraulic snubhers utilizing the mechanical restraints because of the uncertainties on licensing and technical issues.

RGSE has requested that we proceed as expeditously as possible with the resolution of this matter in spite of the fact there are 12 months until the next outage.

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Docket 50-244 MEMORANDUM TO:

FROM:

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 Ledyard B. Marsh, Chief Mechanical Engineering Branch Division of Engineering and Systems Technology R.

H. Wessman, Director Project Directorate 1-3 Division of Reactor Projects I/II

SUBJECT:

GINNA STEAM GENERATOR SNUBBER REPLACEMENT PROGRAM As you are aware, the staff has been reviewing RG8E plans to replace the Ginna steam generator snubbers with rigid structural members (bumpers).

The licensee had originally expected to make this modification under the provisions of 10 CFR 50.59.

Shortly before their February outage it became clear that a license amendment would be required and that several technical questions were not fully resolved.

The licensee did not proceed during the February outage with the replacement of hydraulic snubbers utilizing the mechanical restraints because of the uncertainties on licensing and technical issues.

RGSE has requested that we proceed as expeditously as possible with the resolution of this matter in spite of the fact there are 12 months until the next outage.-

Per our discussion on March 3rd we agreed to the following:

(1)

Your staff will provide the P.M. within 30 days (April 6th) any additional requests for information that is needed to complete your review.

We will promptly transmit your information needs to RGSE.

(2)

The licensee will be requested to submit all of the information as an amendment to the license.

This submittal is expected to include the necessary information on the effects of cold shutdown on the integrity of the steam generator system and associated piping and suppor ts with the mechanical restraints.

V (3)

Every effort will be made to complete the technical review and provide your SER within a 90 day period from the receipt of the licensee amendment package.

I trust that this is in accordance with our di cussion.

R.

H. Wessman, Director Project Directorate 1-3 Division of Reactor Projects I/II cc:

BBoger, SVar ga,
LShao, CMcCracken, MHertzman, CStahle

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