ML18082A633
| ML18082A633 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/09/1980 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | Mittl R Public Service Enterprise Group |
| References | |
| REF-SSINS-1200 NUDOCS 8006300057 | |
| Download: ML18082A633 (3) | |
Text
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DISTRIBUTION:
JUN 9 1980 Docket File NRC PDR Local PDR 8L #3 Fil es RTedesco ASchwencer JKerrigan JLee Docket No.:
50-311 Mr. R. L. Mitt1, General Manager Licensing and Environment ELD IE (3) bee:
NSIC TIC Engineering and Construction Depa_rtme"'t Pu51ic Service Electric and Gas Company 80 Park Pl ace ACRS (16)
Newark, New Jersey 07101
Dear Mr. Mittl:
SUBJECT:
SALEM UNIT 2 STEAM GENERATORS We have completed our review of your submittal, dated April 15, 1980, in which you contend that installation of in.spection ports and plugging of Row 1 tubes in the Salem 2 ste-am _generators is unnecessary at this time.
The staff has concluded that, for the reasons outlined in our March 27, 1980 letter to PSE&G (Olan Parr* to R~ L. Miftl ).," inspectiory ports be installed in the Salem 2 steam generators prior to start-up after the first refueling.
The staff has also c_onclud~d that PSE_&G has not pre-sented any information which demonstrates t~at potential cracking near the top of the U-bend in Row 1 tubes can be avoided.
Therefore, in the interest of as low as reasonably achievable (ALARA) industrial dose exposures, we will continue to require _tliat all Rm~ 1 tubes be plugged prior to issuance of the Salem 2* full pm;ier license.
At the present time, Westinghouse has c:ommitted (letter from T. M. Anderson to R. H. Vollmer, May 12, 1980) to a program to determine the particular susceptibility of Row 1 tubes to crackiD9*
The _p~ogram involves removing numerous tubes from the Trojan plant and subjecting them.to non-destructive and destructive testing to identify the cause of the cracking and to develop
.a field inspection method capable of detecting potential leaking tubes.
The results of this evaluation are expected to _be available in October 1980.
We shall review the program results and re-evaluate at that time the staff's position on Row 1 tube plugging, for Westinghouse steam generators.
Should you have any questions in this.regard, do not hesitate to contact us.
,800680u os7 cc: See next page DL: LB #3 D
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DATE **.*.... 'W-!-'-(*......... _(f._........
Original Signe~ by.
- r A. Schwencer, Acting Chief Licensing Branch No. 3 Division of Licensing DE:MQ VSNoon
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NRC FORM.318 (9-76) NRCM 0240
-i:tus. GOVERNMENT PRINTING OFFICE: 1979-289-36"9
Docket No.:
50-311 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 JUN 9
- 1980 Mr. R. L. Mittl, General Manager Licensing and Environment Engineering and Construction Department Public Service Electric and Gas Company 80 Park Place Newark, New Jersey 07101
Dear Mr. Mittl:
SUBJECT:
SALEM UNIT 2 STEAM GENERATORS We have completed our review of your submittal, dated April 15, 1980, in which you contend that installation of inspection ports and plugging of Row 1 tubes in the Salem 2 steam generators is unnecessary at this time.
The staff has concluded that, for the reasons outlined in our March 27, 1980 letter to PSE&G (Olan Parr to R. L. Mittl), inspection ports be installed in the Salem 2 steam generators pri9r to start-up after the first refueling. The staff has also concluded that PSE&G has not pre-sented any information which demonstrates that potential cracking *near the top of the U-bend in Row 1 tubes can be avoided.
Therefore, in the interest of as low as reasonably achievable (ALARA) industrial dose exposures, we will continue to require that all Row 1 tubes be plugged.
prior to issuance of the Salem 2 full power license.
At the present time, Westinghouse has committed (letter from T. M. Anderson to R. H. Vollmer, May 12, 1980) to a program to determine the particular susceptibility of Row 1 tubes to cracking.
The program involves removi_ng numerous tubes from the Trojan plant and subjecting them to non-destructive and destructive testing to identify the c*ause of the cracking and to develop a field inspection method capable of detecting potential leaking tubes.
The results of this evaluation are expected to be available in October 1980.
We shall review the program results and re-evaluate at that time the staff's position on Row 1 tube plugging for Westinghouse steam generators.
Should you have any questions us.
cc:
See next page in this regard, 6 not hesitate to contact a
A. Schwencer, Acting Chief Licensing Branch No. 3 Division of Licensing
cc:
Richard Fryling, Jr., Esq.
Assistant General Counsel Public Service Electric &-Gas Company 80 Park Pl ace Newark, New Jersey 07100 Mark Wetterhahn, Esq.
Conner, Moore & Cober Suite l 050 1747 Pennsylvania Avenue, N. W.
Washington~ o. c.
20006 Mr~ Leif J. Norrholm c/o U. s*. Nuclear Regulatory Corrmission Region I, Drawer I Hancocks Bridge*, New Jersey *08038