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{{#Wiki_filter:P*ublic Service . Electric and Gas Company Stanley LaBruna Public Service Electric and Gas_ Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-4800 Vice President  
{{#Wiki_filter:P*ublic Service .
-Nuclear Operations JUL 1 0 1990. NLR-N90146 .u.s. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
Electric and Gas Company Stanley LaBruna                     Public Service Electric and Gas_ Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-4800 Vice President - Nuclear Operations JUL 1 0             1990.
REQUEST FOR SUBMITTAL OF INFORMATION WESTINGHOUSE REASSESSMENT OF BULLETIN 88-02 RESPONSE SALEM GENERATING STATION, UNITS 1 & 2 DOCKET NOS. 50-272 & 50-311 In a letter dated March 27, 1990, Westinghouse informed the NRC staff of its plan to reassess and update the analysis that had been done in.response to Bulletin 88-02. The letter identified Salem Units 1 and 2 as category 6 plants for which reassessment had yet to be done. Accordingly, in a letter dated May 10, 1990, the NRC requested PSE&G to submit the reassessment upon receipt from Westinghouse.
NLR-N90146
Westinghouse has informed PSE&G that the Salem Units were erroneously identified as Category 6 plants when they should have been placed in Category 5 since their reevaluations had already been completed (see attached letter dated June 14, 1990}. The results of the reassessments had been transmitted to PSE&G in a *Westinghouse letter dated 6, 1990. PSE&G subsequently relayed the information to the NRC in letter NLR-N90019 dated January. 19, 1990. Thus, PSE&G's response to Bulletin 88-02 is considered complete and no further action is anticipated.
            .u.s.         Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
Should you have any questions regarding this response, please feel free to contact us. Thank you. Attachment 90071.70328 900710 ADGCK 05000272 Q PDC Sincerely, ,-,......_  
REQUEST FOR SUBMITTAL OF INFORMATION WESTINGHOUSE REASSESSMENT OF BULLETIN 88-02 RESPONSE SALEM GENERATING STATION, UNITS 1 & 2 DOCKET NOS. 50-272 & 50-311 In a letter dated March 27, 1990,                                   Westinghouse informed the NRC staff of its plan to reassess and                                   update the analysis that had been done in.response to Bulletin                                   88-02. The letter identified Salem Units 1 and 2 as category 6                                   plants for which reassessment had yet to be done. Accordingly,                                   in a letter dated May 10, 1990, the NRC requested PSE&G to submit                                   the reassessment upon receipt from Westinghouse.
/ --I (...,.._ *  
Westinghouse has informed PSE&G that the Salem Units were erroneously identified as Category 6 plants when they should have been placed in Category 5 since their reevaluations had already been completed (see attached letter dated June 14, 1990}. The results of the reassessments had been transmitted to PSE&G in a
/-{*>;;?-../  
          *Westinghouse letter dated Janua~y 6, 1990. PSE&G subsequently relayed the information to the NRC in letter NLR-N90019 dated January. 19, 1990.
-.
Thus, PSE&G's response to Bulletin 88-02 is considered complete and no further action is anticipated. Should you have any questions regarding this response, please feel free to contact us. Thank you.
. Document Control Desk NLR-N90146 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 Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 JUL 1 o 1990 Westinghouse Electric Corporation Mr. H. G. Berrick Energy Systems ** Box 355 Pittsburgh Pennsylvania 15230*0355 PSE-90-618 June 14,-1990 *public Service Electric & Gas Company P. 0. Box 236 Re: W Letter to NRC NS-NRC-90-3498, March 27, 1990 Hancocks Bridge, NJ 08038 PUBLIC SERVICE ELECTRIC & GAS COMPANY SALEM UNITS 1 & 2 REASSESSMENT OF STEAM GENERATOR TUBE FATIGUE EVALUATION NRC GENERIC LETTER 88-02  
Sincerely,
                                                                              ,-,......_   / ./~/(§7
                                                                                            -- I   (...,.._ *
                                                                      , /   -
                                                                          -{*>;;?-../   .
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Attachment 90071.70328 900710 PD~        ADGCK 05000272 Q                        PDC
 
. Document Control Desk             2 JUL 1 o 1990 NLR-N90146 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
 
Westinghouse           Energy Systems                             Box 355 Electric Corporation                                              Pittsburgh Pennsylvania 15230*0355 PSE-90-618 June 14,- 1990 Mr. H. G. Berrick
*public Service Electric & Gas Company               Re: WLetter    to NRC P. 0. Box 236                                           NS-NRC-90-3498, Hancocks Bridge, NJ 08038                               March 27, 1990 PUBLIC SERVICE ELECTRIC &GAS COMPANY SALEM UNITS 1 & 2 REASSESSMENT OF STEAM GENERATOR TUBE FATIGUE EVALUATION NRC GENERIC LETTER 88-02


==Dear Mr. Berrick:==
==Dear Mr. Berrick:==
Westinghouse rec*ently advised the NRC, by the above referenced letter, and its nuclear utility customers of the plan to update the steam generator tube fatigue analyses done prioi to November, 1988 in response to NRC Bulletin 88-02, "Rapidly Propagating Fatigue Cracks in SteamGenerator Tubes". As was explained in our communications to the NRC and our customers, the reevaluation effort was undertaken largely to address some concern over the uncertainties in AVB position used in the earlier analyses.
Westinghouse rec*ently advised the NRC, by the above referenced letter, and its nuclear utility customers of the plan to update the steam generator tube fatigue analyses done prioi to November, 1988 in response to NRC Bulletin 88-02, "Rapidly Propagating Fatigue Cracks in SteamGenerator Tubes". As was explained in our communications to the NRC and our customers, the reevaluation effort was undertaken largely to address some concern over the uncertainties in AVB position used in the earlier analyses.
* In presenting the plan *for the reevaluation of those plants for which Westinghouse had performed the original analysis, our letter to the NRC placed the plants into six categories, ranging from plants in categories 1 through 4 that required no further analysis, to those in categories 5 & 6 which were already reevaluated, or scheduled to be respectively.
* In presenting the plan *for the reevaluation of those plants for which Westinghouse had performed the original ~-88-02" analysis, our letter                               I to the NRC placed the plants into six categories, ranging from plants in categories 1 through 4 that required no further analysis, to those in categories 5 & 6 which were already reevaluated, or scheduled to be reevalu~ted, respectively.       The Salem Units were erroneously identified as category 6 plants when they should, of course, have been placed in category 5, since their reevaluations were completed and* the results already transmitted to PSE&G by Westinghouse letter NQ. PSE-90-507, dated January 10, 1990. Thus, no further action is antjcipated to be liecessary for PSE&G to address NRC Bulletin 88-02 for the Salem Units 1
The Salem Units were erroneously identified as category 6 plants when they should, of course, have been placed in category 5, since their reevaluations were completed and* the results already transmitted to PSE&G by Westinghouse letter NQ. PSE-90-507, dated January 10, 1990. Thus, no further action is antjcipated to be liecessary for PSE&G to address NRC Bulletin 88-02 for the Salem Units 1 & 2 steam generators.
& 2 steam generators.
Very truly yours, J?JL--J/-< J. N. Steinmetz, Manager Operating Plant Projects I l *' & H. G. Berrick cc: -tl-B_ nag ... J. P. Ronafalvy F. C. Schnart M. P. Morroni J. A. Nichols *e PSE-90-618 June 14, 1990 I}}
Very truly yours, J?JL--J/-
J. N. Steinmetz, Manager Operating Plant Projects
 
l
      ~r. H. G. Berrick
                                  *e PSE-90-618
*'                          June 14, 1990 cc: -tl-B_ nag a~...
J. P. Ronafalvy F. C. Schnart M. P. Morroni J. A. Nichols I}}

Latest revision as of 06:59, 3 February 2020

Forwards Jn Steinmetz of Westinghouse 900614 Ltr Re Reassessment of Util Response to Bulletin 88-002
ML18095A349
Person / Time
Site: Salem  PSEG icon.png
Issue date: 07/10/1990
From: Labruna S
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
IEB-88-002, IEB-88-2, NLR-N90146, NUDOCS 9007170328
Download: ML18095A349 (4)


Text

{{#Wiki_filter:P*ublic Service . Electric and Gas Company Stanley LaBruna Public Service Electric and Gas_ Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-4800 Vice President - Nuclear Operations JUL 1 0 1990. NLR-N90146

           .u.s.         Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

REQUEST FOR SUBMITTAL OF INFORMATION WESTINGHOUSE REASSESSMENT OF BULLETIN 88-02 RESPONSE SALEM GENERATING STATION, UNITS 1 & 2 DOCKET NOS. 50-272 & 50-311 In a letter dated March 27, 1990, Westinghouse informed the NRC staff of its plan to reassess and update the analysis that had been done in.response to Bulletin 88-02. The letter identified Salem Units 1 and 2 as category 6 plants for which reassessment had yet to be done. Accordingly, in a letter dated May 10, 1990, the NRC requested PSE&G to submit the reassessment upon receipt from Westinghouse. Westinghouse has informed PSE&G that the Salem Units were erroneously identified as Category 6 plants when they should have been placed in Category 5 since their reevaluations had already been completed (see attached letter dated June 14, 1990}. The results of the reassessments had been transmitted to PSE&G in a

          *Westinghouse letter dated Janua~y 6, 1990. PSE&G subsequently relayed the information to the NRC in letter NLR-N90019 dated January. 19, 1990.

Thus, PSE&G's response to Bulletin 88-02 is considered complete and no further action is anticipated. Should you have any questions regarding this response, please feel free to contact us. Thank you. Sincerely,

                                                                             ,-,......_   / ./~/(§7
                                                                                            -- I   (...,.._ *
                                                                     , /   -
                                                                          -{*>;;?-../   .

er/~--~- Attachment 90071.70328 900710 PD~ ADGCK 05000272 Q PDC

. Document Control Desk 2 JUL 1 o 1990 NLR-N90146 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

Westinghouse Energy Systems Box 355 Electric Corporation Pittsburgh Pennsylvania 15230*0355 PSE-90-618 June 14,- 1990 Mr. H. G. Berrick

  • public Service Electric & Gas Company Re: WLetter to NRC P. 0. Box 236 NS-NRC-90-3498, Hancocks Bridge, NJ 08038 March 27, 1990 PUBLIC SERVICE ELECTRIC &GAS COMPANY SALEM UNITS 1 & 2 REASSESSMENT OF STEAM GENERATOR TUBE FATIGUE EVALUATION NRC GENERIC LETTER 88-02

Dear Mr. Berrick:

Westinghouse rec*ently advised the NRC, by the above referenced letter, and its nuclear utility customers of the plan to update the steam generator tube fatigue analyses done prioi to November, 1988 in response to NRC Bulletin 88-02, "Rapidly Propagating Fatigue Cracks in SteamGenerator Tubes". As was explained in our communications to the NRC and our customers, the reevaluation effort was undertaken largely to address some concern over the uncertainties in AVB position used in the earlier analyses.

  • In presenting the plan *for the reevaluation of those plants for which Westinghouse had performed the original ~-88-02" analysis, our letter I to the NRC placed the plants into six categories, ranging from plants in categories 1 through 4 that required no further analysis, to those in categories 5 & 6 which were already reevaluated, or scheduled to be reevalu~ted, respectively. The Salem Units were erroneously identified as category 6 plants when they should, of course, have been placed in category 5, since their reevaluations were completed and* the results already transmitted to PSE&G by Westinghouse letter NQ. PSE-90-507, dated January 10, 1990. Thus, no further action is antjcipated to be liecessary for PSE&G to address NRC Bulletin 88-02 for the Salem Units 1

& 2 steam generators. Very truly yours, J?JL--J/- J. N. Steinmetz, Manager Operating Plant Projects

l

     ~r. H. G. Berrick
                                 *e PSE-90-618
*'                          June 14, 1990 cc:  -tl-B_ nag a~...

J. P. Ronafalvy F. C. Schnart M. P. Morroni J. A. Nichols I}}