ML18101A524
| ML18101A524 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 01/30/1995 |
| From: | Labruna S Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LR-N95007, NUDOCS 9502070087 | |
| Download: ML18101A524 (3) | |
Text
Public Service Electric and Gas Company I
Stanley LaBruna Public Service Electric and Gas' Company
- P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1700 Vice President - Nuclear Engineering JAN 3 0 1995 LR-N95007 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
ALLOY 600 STEAM GENERATOR MECHANICAL TUBE PLUGS SALEM GENERATING STATION UNIT NOS. 1 & 2 FACILITY OPERATING LICENSE NOS. DPR-70 & DPR-75 DOCKET NOS. 50-272 & 50-311 PSE&G hereby submits the following information in support of the Westinghouse Owners Group/Industry initiatives related to the most recent industry experience of primary water stress corrosion cracking (PWSCC) of Alloy 600 steam generator mechanical tube plugs.
The mechanical plugs were manufactured from Heat NX 2387, and exhibited circumferential cracking due to PWSCC.
- 1)
Salem Unit 1 has replaced the mechanical plugs manufactured from Alloy 600 thermally treated (TT) material with Alloy 690 plugs or repaired the plugs using the Plug-in-Plug (PIP) method on the hot leg tube ends.
A total of 413 plugs are located on the cold leg tube ends which have not yet been replaced/repaired.
Salem Unit 2 currently has a total of 44 mechanical plugs manufactured from Alloy 600 TT material which have not been replaced with Alloy 690 plugs or repaired using the Plug-in-Plug (PIP) method on the hot leg tube ends.
A total of 381 plugs are located on the cold leg tube ends which have not yet been replaced/repaired.
The schedule to repair/replace these plugs will be based on a revision to the corrosion algorithm presented in WCAP-12244, Rev. 3, or technical justification will be provided to allow continued use.
Westinghouse has communicated to us that they intend to issue Addendum 3 to WCAP-12244, Rev. 3 in January 1995 (See #3 below).
- 2)
The recent industry plug cracking experience does not adversely impact the Justification for Continued Operation D
\\.,
Document Control Desk LR-N95,007 2
JAN 3 0 1995 (JCO) as provided in Sections 3.0 and 4.0 of WCAP 12244, Revision 3 and Addenda 1 and 2, and is not an immediate safety concern for Salem Units 1 and 2.
The following are the key points of the JCO:
Leakage past the plug into an inactive tube equalizes the pressure and precludes plug top release.
Plugs are expected to leak prior to any full circumferential cracking.
- In the unlikely event that a plug top release occurs and results in perforation of the inactive tube, this event would be bounded by the analysis of the Steam Generator Tube Rupture (SGTR) event contained in UFSAR Section 15.4.4.
- Existing Emergency Operating Procedures are adequate to mitigate the consequences of the plug top release event, and bring the plant to a safe shutdown condition.
- 3)
PSE&G will evaluate the impact of Addendum 3 of WCAP-12244, Revision 3~ scheduled for issuance by Westinghouse in January 1995, on the current Salem Units 1 and 2 Action Plans to replace/repair the Alloy 600 mechanical tubes developed in response to NRC Bulletin 89-01 and Supplements.
The results of this evaluation and any changes to the Action Plan, if necessary, will be submitted within 30 days of the next scheduled outages for Units 1 and 2.
Based on the meeting between Westinghouse, Industry and the NRC on December 22, 1994, it is not expected that any additional actions will be required for Salem Unit 1 during the upcoming outage scheduled for April, 1995 since the Alloy 600 mechanical plugs have been replaced/repaired on the hot leg tube ends of all four steam generators.
Should you have any questions on this submittal, please contact us.
Sincerely, 95-4933
- , *.. ~* -...
,_: ~----' '* -**.:.*,._* -~* *.
-I*
I Document control Desk LR;.-N950.07 3
C Mr. T. T. Martin, Administrator - Region 1
- u. s. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. L. N. Olshan, Licensing Project Manager -
Salem
- u. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. c. s. Marschall (S09)
USNRC Senior Resident Inspector Mr. Kent Tosch, Manager, IV NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 JANS 01995