ML18095A375: Difference between revisions

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{{#Wiki_filter:. -' Public Service Electric and Gas Company Thomas M. Crimmins, Jr. Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-4700 Vice President  
{{#Wiki_filter:.-
-Nuclear Engineering JUL 1 8 1990 NLR-N90.140 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
                                                        '   Public Service Electric and Gas Company Thomas M. Crimmins, Jr.             Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-4700 Vice President - Nuclear Engineering JUL 1 8 1990 NLR-N90.140 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
STATUS OF COMMITMENTS NUREG 0737 ITEM II.D.1 SALEM GENERATING STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 The purpose of this letter is to provide the status of commitments made to the NRC by PSE&G in a letter dated January 9, 1990 (NLR-N89223) pertaining to NUREG 0737 Item II.D.1. Attachment 1 contains the commitments and their implementation status. This letter is being submitted as follow-up to a phone conference which took place between Mr. Jim Stone, Licensing Project Manager, and members of the PSE&G Nuclear Licensing and Regulation Department on June 28, 1990. Should you have any questions, please feel free to contact us. Thank you. Attachment 9Q08010243 900718 ADOCK 0500dl72 F'DC L > -* Document Control Desk NLR-N90140 C Mr. J. C. Stone Licensing Project Manager Mr. T. Johnson Senior Resident Inspector Mr. T. Martin, Administrator Region I Mr. Kent Tosch, Chief 2 New Jersey Department of Environmental Protection Division of Environmental  
STATUS OF COMMITMENTS NUREG 0737 ITEM II.D.1 SALEM GENERATING STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 The purpose of this letter is to provide the status of commitments made to the NRC by PSE&G in a letter dated January 9, 1990 (NLR-N89223) pertaining to NUREG 0737 Item II.D.1. Attachment 1 contains the commitments and their implementation status.
*Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 JUL 1 8 1990
This letter is being submitted as follow-up to a phone conference which took place between Mr. Jim Stone, Licensing Project Manager, and members of the PSE&G Nuclear Licensing and Regulation Department on June 28, 1990.
* ATTACHMENT 1 COMMITMENTS (Reference PSE&G Letter NLR-N89223, January 9, 1990) "The evaluations presented therein have determined that minor modifications will be made to strengthen the Unit 1 piping supports downstream of the anchor at elevation 131' 4 11* Modifications will be performed during the 1992 refueling outage. As stated previously, the thermal-hydraulic inputs for Unit 2 are unavailable.
Should you have any questions, please feel free to contact us.
PSE&G will reconstruct the Unit 2 thermal-hydraulic analysis and evaluate the Unit 2 piping downstream of elevation 131. This review will be completed by June 30, 1990. Any modifications found to be necessary will be performed during the Unit 2 Fall 1991 refueling outage." STATUS OF COMMITMENT IMPLEMENTATION It was explained in the referenced letter that with the formation/relocation of the Nuclear Department, magnetic media files documenting the thermal hydraulic analysis inputs for the Unit 2 *poRV discharge piping were unretrievable.
Thank you.
Rather than pursue a similarity approach between Units 1 and 2 to obtain the required data, the decision was made to reconstruct the Unit 2 analysis using the same assumptions used in the Unit 1 analysis.
Attachment 9Q08010243 900718
            ~DR ADOCK 0500dl72 F'DC
 
L > -
* Document Control Desk           2                  JUL 1 8 1990 NLR-N90140 C Mr. J. C. Stone Licensing Project Manager Mr. T. Johnson Senior Resident Inspector Mr. T. Martin, Administrator Region I Mr. Kent Tosch, Chief New Jersey Department of Environmental Protection Division of Environmental *Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625
* ATTACHMENT 1 COMMITMENTS (Reference PSE&G Letter NLR-N89223, January 9, 1990)
"The evaluations presented therein have determined that minor modifications will be made to strengthen the Unit 1 piping supports downstream of the anchor at elevation 131' 4 11
* Modifications will be performed during the 1992 refueling outage.
As stated previously, the thermal-hydraulic inputs for Unit 2 are unavailable. PSE&G will reconstruct the Unit 2 thermal-hydraulic analysis and evaluate the Unit 2 piping downstream of elevation 131. This review will be completed by June 30, 1990. Any modifications found to be necessary will be performed during the Unit 2 Fall 1991 refueling outage."
STATUS OF COMMITMENT IMPLEMENTATION It was explained in the referenced letter that with the formation/relocation of the Nuclear Department, magnetic media files documenting the thermal hydraulic analysis inputs for the Unit 2 *poRV discharge piping were unretrievable. Rather than pursue a similarity approach between Units 1 and 2 to obtain the required data, the decision was made to reconstruct the Unit 2 analysis using the same assumptions used in the Unit 1 analysis.
Since transmittal of the referenced letter, copies of the original Unit 2 thermal hydraulic analysis were obtained from ABB/IMPELL and reviewed by PSE&G. Thus, it is not necessary to reconstruct the analysis.
Since transmittal of the referenced letter, copies of the original Unit 2 thermal hydraulic analysis were obtained from ABB/IMPELL and reviewed by PSE&G. Thus, it is not necessary to reconstruct the analysis.
The retrieved information, however, has been made partially invalid by the issuance of the NRC's Safety Evaluation Report on NUREG 0737, Item II.D.1 for Salem Units 1 and 2 {May 10, 1990) which contains 4 open items. Completion of these open items will require more conservative analytical assumptions to be used for the affected piping, i.e. inclusion of the effects of the water loop-seal upstream of the PORVs. This requirement, which will necessitate re-analysis of both Unit 1 and 2 Safety/PORV piping and supports, may result in more severe impacts upon the piping/support designs than previously thought. Therefore, the commitments made in the referenced letter are now bounded by the more stringent requirements imposed by the SER open items and will be met by completion of the open items. PSE&G will notify the NRC if, in the course of completing these items, it becomes apparent that the current commitment dates will not be met.}}
The retrieved information, however, has been made partially invalid by the issuance of the NRC's Safety Evaluation Report on NUREG 0737, Item II.D.1 for Salem Units 1 and 2 {May 10, 1990) which contains 4 open items. Completion of these open items will require more conservative analytical assumptions to be used for the affected piping, i.e. inclusion of the effects of the water loop-seal upstream of the PORVs. This requirement, which will necessitate re-analysis of both Unit 1 and 2 Safety/PORV piping and supports, may result in more severe impacts upon the piping/support designs than previously thought.
Therefore, the commitments made in the referenced letter are now bounded by the more stringent requirements imposed by the SER open items and will be met by completion of the open items.
PSE&G will notify the NRC if, in the course of completing these items, it becomes apparent that the current commitment dates will not be met.}}

Revision as of 11:52, 21 October 2019

Provides Status of Commitments Made to NRC by Util in 900109 Ltr Re NUREG-0737,Item II.D.1,per 900628 Telcon
ML18095A375
Person / Time
Site: Salem  PSEG icon.png
Issue date: 07/18/1990
From: Crimmins T
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM NLR-N90140, NUDOCS 9008010243
Download: ML18095A375 (3)
v • d • e


Text

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' Public Service Electric and Gas Company Thomas M. Crimmins, Jr. Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-4700 Vice President - Nuclear Engineering JUL 1 8 1990 NLR-N90.140 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

STATUS OF COMMITMENTS NUREG 0737 ITEM II.D.1 SALEM GENERATING STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 The purpose of this letter is to provide the status of commitments made to the NRC by PSE&G in a letter dated January 9, 1990 (NLR-N89223) pertaining to NUREG 0737 Item II.D.1. Attachment 1 contains the commitments and their implementation status.

This letter is being submitted as follow-up to a phone conference which took place between Mr. Jim Stone, Licensing Project Manager, and members of the PSE&G Nuclear Licensing and Regulation Department on June 28, 1990.

Should you have any questions, please feel free to contact us.

Thank you.

Attachment 9Q08010243 900718

~DR ADOCK 0500dl72 F'DC

L > -

  • Document Control Desk 2 JUL 1 8 1990 NLR-N90140 C Mr. J. C. Stone Licensing Project Manager Mr. T. Johnson Senior Resident Inspector Mr. T. Martin, Administrator Region I Mr. Kent Tosch, Chief New Jersey Department of Environmental Protection Division of Environmental *Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625
  • ATTACHMENT 1 COMMITMENTS (Reference PSE&G Letter NLR-N89223, January 9, 1990)

"The evaluations presented therein have determined that minor modifications will be made to strengthen the Unit 1 piping supports downstream of the anchor at elevation 131' 4 11

  • Modifications will be performed during the 1992 refueling outage.

As stated previously, the thermal-hydraulic inputs for Unit 2 are unavailable. PSE&G will reconstruct the Unit 2 thermal-hydraulic analysis and evaluate the Unit 2 piping downstream of elevation 131. This review will be completed by June 30, 1990. Any modifications found to be necessary will be performed during the Unit 2 Fall 1991 refueling outage."

STATUS OF COMMITMENT IMPLEMENTATION It was explained in the referenced letter that with the formation/relocation of the Nuclear Department, magnetic media files documenting the thermal hydraulic analysis inputs for the Unit 2 *poRV discharge piping were unretrievable. Rather than pursue a similarity approach between Units 1 and 2 to obtain the required data, the decision was made to reconstruct the Unit 2 analysis using the same assumptions used in the Unit 1 analysis.

Since transmittal of the referenced letter, copies of the original Unit 2 thermal hydraulic analysis were obtained from ABB/IMPELL and reviewed by PSE&G. Thus, it is not necessary to reconstruct the analysis.

The retrieved information, however, has been made partially invalid by the issuance of the NRC's Safety Evaluation Report on NUREG 0737, Item II.D.1 for Salem Units 1 and 2 {May 10, 1990) which contains 4 open items. Completion of these open items will require more conservative analytical assumptions to be used for the affected piping, i.e. inclusion of the effects of the water loop-seal upstream of the PORVs. This requirement, which will necessitate re-analysis of both Unit 1 and 2 Safety/PORV piping and supports, may result in more severe impacts upon the piping/support designs than previously thought.

Therefore, the commitments made in the referenced letter are now bounded by the more stringent requirements imposed by the SER open items and will be met by completion of the open items.

PSE&G will notify the NRC if, in the course of completing these items, it becomes apparent that the current commitment dates will not be met.

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