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{{#Wiki_filter:-! I*
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* Public Service
* Public Service
* Electric and Gas Company
* Electric and Gas Company
* E. C. Simpson Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1700 Senior Vice President  
* E. C. Simpson                               Public Service Electric and Gas Company   P.O. Box 236, Hancocks Bridge, NJ 08038               609-339-1700 Senior Vice President - Nuclear Engineering LR-N980044 LCR S97-21 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 SUPPLEMENTAL INFORMATION TO REQUEST FOR LICENSE AMENDMENT STEAM GENERATOR SURVEILLANCE INTE;~\{AL~
-Nuclear Engineering LR-N980044 LCR S97-21 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 SUPPLEMENTAL INFORMATION TO REQUEST FOR LICENSE AMENDMENT STEAM GENERATOR SURVEILLANCE SALEM GENERATING STATION UNIT 2 FACILITY OPERA TING LICENSE NOS. DPR-75 DOCKET NO. 50-311 Gentlemen:
SALEM GENERATING STATION UNIT 2 FACILITY OPERATING LICENSE NOS. DPR-75 DOCKET NO. 50-311 Gentlemen:
By letter dated October 29, 1997 (Our ref:LR-N97557; NRC Ref TAC# M99888), Public Service Electric and Gas Company (PSE&G) requested a revision to the Technical Specifications (TS) for Salem Generating Station Unit 2. The requested revision is a one time change to the Unit 2 Steam Generator inspection schedule.
By letter dated October 29, 1997 (Our ref:LR-N97557; NRC Ref TAC# M99888), Public Service Electric and Gas Company (PSE&G) requested a revision to the Technical Specifications (TS) for Salem Generating Station Unit 2. The requested revision is a one time change to the Unit 2 Steam Generator inspection schedule.
On January 22, 1998, PSE&G and NRC personnel discussed the Salem Unit 2 primary to secondary leakage history. As a result of this telephone discussion, PSE&G was requested to include the information verbally discussed relative to the Salem 2 primary to secondary leakage history as a supplement to the original submittal.
On January 22, 1998, PSE&G and NRC personnel discussed the Salem Unit 2 primary to secondary leakage history. As a result of this telephone discussion, PSE&G was requested to include the information verbally discussed relative to the Salem 2 primary to secondary leakage history as a supplement to the original submittal. Attachment 1 to this letter contains the requested information.
Attachment 1 to this letter contains the requested information.
Additionally, in the original submittal, PSE&G requested that the steam generator inspection be extended to within 24 months of Mode 2 for Unit 2 fuel cycle 10. NRC requested PSE&G to clarify this statement by the addition of the phrase "or the next scheduled refueling outage, whichever is first." Accordingly, PSE&G modifies Insert A of LR-N97557 to read "... inspection will be required to be performed within 24 months of Mode 2 (this would be by August 17, 1999), or during the next scheduled refueling outage, whichever is first for Unit 2 fuel cycle 1O." Attachment 2 contains the new Insert A.                                                                                                                     AtJV I ] f I
Additionally, in the original submittal, PSE&G requested that the steam generator inspection be extended to within 24 months of Mode 2 for Unit 2 fuel cycle 10. NRC requested PSE&G to clarify this statement by the addition of the phrase "or the next scheduled refueling outage, whichever is first." Accordingly, PSE&G modifies Insert A of LR-N97557 to read " ... inspection will be required to be performed within 24 months of Mode 2 (this would be by August 17, 1999), or during the next scheduled refueling I outage, whichever is first for Unit 2 fuel cycle 1 O." Attachment 2 contains the new f Insert A. AtJV I ]1 P 98 0 02060087 980127 '----------------, p R ADOCK ..
1 9802060087 980127                                                             '----------------,
1 ' 1111111 lllllillll lllllllllllllll llll llll '*&&5973. Printedon Recycled Paper Document Control Desk LR-N980044 2
9soo~5~
* JAN 871998 PSE&G has evaluated this additional information and determined that it does not invalidate the original no significant hazards determinati.on of LR-N97557.
P0 p R ADOCK .                           1                                       ' 1111111 lllllillll lllllllllllllll llll llll
Should you have any questions regarding this request, we will be pleased to discuss them with you. Affidavit Attachments (2) C Mr. H. J. Miller, Administrator  
                                                                                                  '*&&5973.
-Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. P. Milano, Licensing Project Manager -Salem U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 Ms. M. Evans (X24) USNRC Senior Resident Inspector Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering PO Box415 Trenton, NJ 08625
    ~ Printedon
*
    ~ Recycled Paper
* STATE OF NEW JERSEY) )SS COUNTY OF SALEM ) REF: LR-N980044 LCR S97-21 E. C. Simpson, being duly sworn according to law deposes and says: I am Senior Vice President  
* JAN 871998 Document Control Desk               2 LR-N980044 PSE&G has evaluated this additional information and determined that it does not invalidate the original no significant hazards determinati.on of LR-N97557.
-Nuclear Engineering of Public Service Electric and Gas Company, and as such, I find the matters set forth in the above referenced letter, concerning Salem Generating Station, Unit 2, are true to the best of my knowledge, information and belief. Subscribed and Sworn to before me KIMBERLY JO BROWN NOTARY PUBLIC OF NEW ,JERSEY My Commission expires on ____ N_1v_c_orr_.m_iss_ion_E_xp_irn_1  
Should you have any questions regarding this request, we will be pleased to discuss them with you.
.. _*\:;_:ii_21_, _rn_M __
Affidavit Attachments (2)
* Document Control Desk LR-N980044  
C     Mr. H. J. Miller, Administrator - Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. P. Milano, Licensing Project Manager - Salem U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 Ms. M. Evans (X24)
\. ATTACHMENT 1 SALEM UNIT 2 PRIMARY TO SECONDARY LEAKAGE HISTORY September-October 1984
USNRC Senior Resident Inspector Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering PO Box415 Trenton, NJ 08625
 
                        *
* REF:      LR-N980044 LCR S97-21 STATE OF NEW JERSEY)
                            )SS COUNTY OF SALEM             )
E. C. Simpson, being duly sworn according to law deposes and says:
I am Senior Vice President - Nuclear Engineering of Public Service Electric and Gas Company, and as such, I find the matters set forth in the above referenced letter, concerning Salem Generating Station, Unit 2, are true to the best of my knowledge, information and belief.
Subscribed and Sworn to before me KIMBERLY JO BROWN NOTARY PUBLIC OF NEW ,JERSEY My Commission expires on ____N_1v_c_orr_.m_iss_ion_E_xp_irn_1.._*\:;_:ii_21_,_rn_M_ _
 
                      *                                     \.
Document Control Desk LR-N980044 ATTACHMENT 1 SALEM UNIT 2 PRIMARY TO SECONDARY LEAKAGE HISTORY September-October 1984
* Primary to Secondary Leakage identified in 24 Steam Generator
* Primary to Secondary Leakage identified in 24 Steam Generator
* Maximum leakage -10 GPO
* Maximum leakage - 10 GPO
* Determined to be due to a foreign object July-October 1987
* Determined to be due to a foreign object July-October 1987
* Primary to Secondary Leakage identified in 24 Steam Generator
* Primary to Secondary Leakage identified in 24 Steam Generator
* Maximum leakage -65 GPO
* Maximum leakage - 65 GPO
* Determined to be due to Row 1 U-bend PWSCC March-September 1988
* Determined to be due to Row 1 U-bend PWSCC March-September 1988
* Primary to Secondary Leakage identified in 22 and 24 Steam Generators
* Primary to Secondary Leakage identified in 22 and 24 Steam Generators
* Maximum leakage -16 GPO on 24 Steam Generator
* Maximum leakage - 16 GPO on 24 Steam Generator
* All Row 1 tubes plugged Current Status
* All Row 1 tubes plugged Current Status
* No measurable*
* No measurable* Primary to Secondary Leakage since 1988
Primary to Secondary Leakage since 1988 *A primary to secondary leak is measurable if a resample shows reliably detected gamma activity containing isotopes with a half life of <1 day (such as Na-24 and 1-133).
*A primary to secondary leak is measurable if a resample shows reliably detected gamma activity containing isotopes with a half life of <1 day (such as Na-24 and 1-133).
. ' "
 
* Document Control Desk LR-N980044 "INSERT A"
.
* ATTACHMENT 2 STEAM GENERATOR SURVEILLANCE PERIOD AMENDMENT FOR SALEM NUCLEAR GENERATING STATION UNIT 2 FUEL CYCLE 2R10 Salem Unit 2 was removed from service in June of 1995 for a comprehensive review of plant methods and policies.
"
In May of 1996, a 100% bobbin coil and additional specialty examinations inspection of the Salem Unit 2 steam generators was completed.
  '
Permission to restart Unit 2 was given by the NRC in June of 1997 and Mode 2 first achieved on August 17, 1997. After the May 1996 inspection, Unit 2 steam generators were placed in lay-up, using EPRI guidelines, to protect the steam generators from deterioration.
                            *
PSE&G has a high level of confidence that corrosion growth and new corrosion initiation during the time of lay-up were essentially halted, and the condition of the steam generators has not changed since the May 1996 inspection.
* Document Control Desk LR-N980044 ATTACHMENT 2 "INSERT A" STEAM GENERATOR SURVEILLANCE PERIOD AMENDMENT FOR SALEM NUCLEAR GENERATING STATION UNIT 2 FUEL CYCLE 2R10 Salem Unit 2 was removed from service in June of 1995 for a comprehensive review of plant methods and policies. In May of 1996, a 100% bobbin coil and additional specialty examinations inspection of the Salem Unit 2 steam generators was completed. Permission to restart Unit 2 was given by the NRC in June of 1997 and Mode 2 first achieved on August 17, 1997. After the May 1996 inspection, Unit 2 steam generators were placed in lay-up, using EPRI guidelines, to protect the steam generators from deterioration. PSE&G has a high level of confidence that corrosion growth and new corrosion initiation during the time of lay-up were essentially halted, and the condition of the steam generators has not changed since the May 1996 inspection.
Thus, in order to avoid an unnecessary mid-cycle steam generator inspection forced outage, Technical Specification 3/4.4.6 is hereby amended such that the next steam generator inspection will be required to be performed within 24 months of Mode 2 (this would be by August 17, 1999), or during the next scheduled refueling outage, whichever is first for Unit 2 fuel cycle 10. Subsequent steam generator inspections will be scheduled accordingly.}}
Thus, in order to avoid an unnecessary mid-cycle steam generator inspection forced outage, Technical Specification 3/4.4.6 is hereby amended such that the next steam generator inspection will be required to be performed within 24 months of Mode 2 (this would be by August 17, 1999), or during the next scheduled refueling outage, whichever is first for Unit 2 fuel cycle 10. Subsequent steam generator inspections will be scheduled accordingly.}}

Revision as of 08:02, 21 October 2019

Forwards Response to 980122 Telcon RAI Re Plant Primary to Secondary Leakage History,Per 971029 Lar.New Insert a Which Modifies Listed Statement,Encl
ML18106A297
Person / Time
Site: Salem PSEG icon.png
Issue date: 01/27/1998
From: Eric Simpson
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LCR-S97-21, LR-N980044, TAC-M99888, NUDOCS 9802060087
Download: ML18106A297 (5)
v • d • e


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I*

  • Public Service
  • Electric and Gas Company
  • E. C. Simpson Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1700 Senior Vice President - Nuclear Engineering LR-N980044 LCR S97-21 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 SUPPLEMENTAL INFORMATION TO REQUEST FOR LICENSE AMENDMENT STEAM GENERATOR SURVEILLANCE INTE;~\{AL~

SALEM GENERATING STATION UNIT 2 FACILITY OPERATING LICENSE NOS. DPR-75 DOCKET NO. 50-311 Gentlemen:

By letter dated October 29, 1997 (Our ref:LR-N97557; NRC Ref TAC# M99888), Public Service Electric and Gas Company (PSE&G) requested a revision to the Technical Specifications (TS) for Salem Generating Station Unit 2. The requested revision is a one time change to the Unit 2 Steam Generator inspection schedule.

On January 22, 1998, PSE&G and NRC personnel discussed the Salem Unit 2 primary to secondary leakage history. As a result of this telephone discussion, PSE&G was requested to include the information verbally discussed relative to the Salem 2 primary to secondary leakage history as a supplement to the original submittal. Attachment 1 to this letter contains the requested information.

Additionally, in the original submittal, PSE&G requested that the steam generator inspection be extended to within 24 months of Mode 2 for Unit 2 fuel cycle 10. NRC requested PSE&G to clarify this statement by the addition of the phrase "or the next scheduled refueling outage, whichever is first." Accordingly, PSE&G modifies Insert A of LR-N97557 to read "... inspection will be required to be performed within 24 months of Mode 2 (this would be by August 17, 1999), or during the next scheduled refueling outage, whichever is first for Unit 2 fuel cycle 1O." Attachment 2 contains the new Insert A. AtJV I ] f I

1 9802060087 980127 '----------------,

9soo~5~

P0 p R ADOCK . 1 ' 1111111 lllllillll lllllllllllllll llll llll

'*&&5973.

~ Printedon

~ Recycled Paper

  • JAN 871998 Document Control Desk 2 LR-N980044 PSE&G has evaluated this additional information and determined that it does not invalidate the original no significant hazards determinati.on of LR-N97557.

Should you have any questions regarding this request, we will be pleased to discuss them with you.

Affidavit Attachments (2)

C Mr. H. J. Miller, Administrator - Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. P. Milano, Licensing Project Manager - Salem U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 Ms. M. Evans (X24)

USNRC Senior Resident Inspector Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering PO Box415 Trenton, NJ 08625

)SS COUNTY OF SALEM )

E. C. Simpson, being duly sworn according to law deposes and says:

I am Senior Vice President - Nuclear Engineering of Public Service Electric and Gas Company, and as such, I find the matters set forth in the above referenced letter, concerning Salem Generating Station, Unit 2, are true to the best of my knowledge, information and belief.

Subscribed and Sworn to before me KIMBERLY JO BROWN NOTARY PUBLIC OF NEW ,JERSEY My Commission expires on ____N_1v_c_orr_.m_iss_ion_E_xp_irn_1.._*\:;_:ii_21_,_rn_M_ _

  • \.

Document Control Desk LR-N980044 ATTACHMENT 1 SALEM UNIT 2 PRIMARY TO SECONDARY LEAKAGE HISTORY September-October 1984

  • Maximum leakage - 10 GPO
  • Determined to be due to a foreign object July-October 1987
  • Maximum leakage - 65 GPO
  • Determined to be due to Row 1 U-bend PWSCC March-September 1988
  • All Row 1 tubes plugged Current Status
  • No measurable* Primary to Secondary Leakage since 1988
  • A primary to secondary leak is measurable if a resample shows reliably detected gamma activity containing isotopes with a half life of <1 day (such as Na-24 and 1-133).

.

"

'

  • Document Control Desk LR-N980044 ATTACHMENT 2 "INSERT A" STEAM GENERATOR SURVEILLANCE PERIOD AMENDMENT FOR SALEM NUCLEAR GENERATING STATION UNIT 2 FUEL CYCLE 2R10 Salem Unit 2 was removed from service in June of 1995 for a comprehensive review of plant methods and policies. In May of 1996, a 100% bobbin coil and additional specialty examinations inspection of the Salem Unit 2 steam generators was completed. Permission to restart Unit 2 was given by the NRC in June of 1997 and Mode 2 first achieved on August 17, 1997. After the May 1996 inspection, Unit 2 steam generators were placed in lay-up, using EPRI guidelines, to protect the steam generators from deterioration. PSE&G has a high level of confidence that corrosion growth and new corrosion initiation during the time of lay-up were essentially halted, and the condition of the steam generators has not changed since the May 1996 inspection.

Thus, in order to avoid an unnecessary mid-cycle steam generator inspection forced outage, Technical Specification 3/4.4.6 is hereby amended such that the next steam generator inspection will be required to be performed within 24 months of Mode 2 (this would be by August 17, 1999), or during the next scheduled refueling outage, whichever is first for Unit 2 fuel cycle 10. Subsequent steam generator inspections will be scheduled accordingly.

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