ML18079A596: Difference between revisions

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=Text=
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{{#Wiki_filter:Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201 /430-7000 July 19, 1979 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Corrunission Washington, D.C. 20555 Attention:
{{#Wiki_filter:Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201 /430-7000 July 19, 1979 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Corrunission Washington, D.C.               20555 Attention:           Mr. Olan D. Parr, Chief Light Water Reactors Branch 3 Division of Project Management STEAM GENERATOR CHANNEL HEAD INSPECTION N0.2 UNIT SALEM NUCLEAR GENERATING STATION We have reviewed the stainless steel cladding cracks in the No. 2 Unit steam generator channel heads. As a result of a meeting with members of your staff on June 14, 1979, we wish to inform you that we will monitor a selected area in the No. 21 steam generator channel head by ultrasonic examination.
Mr. Olan D. Parr, Chief Light Water Reactors Branch 3 Division of Project Management STEAM GENERATOR CHANNEL HEAD INSPECTION N0.2 UNIT SALEM NUCLEAR GENERATING STATION We have reviewed the stainless steel cladding cracks in the No. 2 Unit steam generator channel heads. As a result of a meeting with members of your staff on June 14, 1979, we wish to inform you that we will monitor a selected area in the No. 21 steam generator channel head by ultrasonic examination.
The area selected is in the lower portion of the cold leg (outlet) side of the No. 21 steam generator. This selection was made on the basis of a prominent interbead liquid penetrant indication between the outlet nozzle and the access manway.
The area selected is in the lower portion of the cold leg (outlet) side of the No. 21 steam generator.
We are in the process of developing the inspection program such that a base line examination can be performed prior to startup of the Unit. It is our intent to perform such examinations during each of the first three refueling outages to verify that the clad crack does not propogate into the base metal.
This selection was made on the basis of a prominent interbead liquid penetrant indication between the outlet nozzle and the access manway. We are in the process of developing the inspection program such that a base line examination can be performed prior to startup of the Unit. It is our intent to perform such examinations during each of the first three refueling outages to verify that the clad crack does not propogate into the base metal. Proposed technical specifications will be transmitted to you in the near future. Should you have any questions in this regard, please do not hesitate to contact us. Very truly yours, '/(/M; R. L. Mitt* General Manager -Licensing and Environment Engineering and Construction 190:J-l!Ji'8 Fl ll:\RSOI' St:ll\lCE O'
Proposed technical specifications will be transmitted to you in the near future.
7 9 0 7 2 5 (r-3°3() 95-2001 (200M) 2-78
Should you have any questions in this regard, please do not hesitate to contact us.
* :50-3 /} UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 FILE July 18, 1979 ALL PRESSURIZED WATER REACTOR LICENSEES Gentlemen:
Very truly yours,
Enclosed is a*copy of Revision 2 of the Draft Radiological Effluent Technical Specifications, (NUREG-0472, PWR; NUREG-0473, BWR). This revision embodies corrections of errors found in previous revisions, revisions in format for consistency with Appendix 11 A 11 Standard Technical Specifications, and some *rewriting for clarification.
                                                        '/(/M; R. L. Mitt*
If you have prepared Radiological Effluent Technical Specifications to a previous revision but have not submitted them to NRC, do not convert them fo this Revision 2 format. You should submit them in their present format since the information required for Revision 2 is available in previous revisions.
General Manager -
Otherwise, Revision 2 should be used to prepare your Technical Specification submittal.
Licensing and Environment Engineering and Construction O'
In i:hose.*cases where submittals Effluent Technical Specifications in a previous format are made to NRC, the final specifications, after and reviews have been completed, will be based on Revision 2. If you have any questions, please contact us.  
                                                                                            '0~~D 190:J-l!Ji'8 Fl     ll:\RSOI' St:ll\lCE 7 9 07 2 5       (r-3°3()
95-2001 (200M) 2-78
* UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555
:50-3 /}
FILE July 18, 1979 ALL PRESSURIZED WATER REACTOR LICENSEES Gentlemen:
Enclosed is a*copy of Revision 2 of the Draft Radiological Effluent Technical Specifications, (NUREG-0472, PWR; NUREG-0473, BWR). This revision embodies corrections of errors found in previous revisions, revisions in format for consistency with Appendix 11 A11 Standard Technical Specifications, and some
*rewriting for clarification.
If you have prepared Radiological Effluent Technical Specifications to a previous revision but have not submitted them to NRC, do not convert them fo this Revision 2 format. You should submit them in their present format since the information required for Revision 2 is available in previous revisions. Otherwise, Revision 2 should be used to prepare your Technical Specification submittal.
J In i:hose.*cases where submittals of..:Radiologl~al Effluent Technical Specifications in a previous format are made to NRC, the final specifications, after negotia-
~ions and reviews have been completed, will be based on Revision 2.
If you have any questions, please contact us.
Sincerely,
                                                              ,
w.01.fr~~
William P. Garrunill, Acting Assistant Director for Operating Reactor Projects Division of Operating Reactors


==Enclosure:==
==Enclosure:==


NUREG-0472, Revision 2 { ,f)*L CJ s f'-,,___f, ) Sincerely, ,
NUREG-0472, Revision 2
William P. Garrunill, Acting Assistant Director for Operating Reactor Projects Division of Operating Reactors J}}
{ ,f)L io~z CJ s f'-,,___f, )}}

Revision as of 15:16, 21 October 2019

Responds to 790614 Meeting Re Stainless Steel Cladding Cracks.Notifies That Util Will Monitor Selected Area in Steam Generator Channel Head 21 by Ultrasonic Examination
ML18079A596
Person / Time
Site: Salem PSEG icon.png
Issue date: 07/19/1979
From: Mittl R
Public Service Enterprise Group
To: Parr O
Office of Nuclear Reactor Regulation
References
NUDOCS 7907250330
Download: ML18079A596 (2)
v • d • e


Text

Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201 /430-7000 July 19, 1979 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Corrunission Washington, D.C. 20555 Attention: Mr. Olan D. Parr, Chief Light Water Reactors Branch 3 Division of Project Management STEAM GENERATOR CHANNEL HEAD INSPECTION N0.2 UNIT SALEM NUCLEAR GENERATING STATION We have reviewed the stainless steel cladding cracks in the No. 2 Unit steam generator channel heads. As a result of a meeting with members of your staff on June 14, 1979, we wish to inform you that we will monitor a selected area in the No. 21 steam generator channel head by ultrasonic examination.

The area selected is in the lower portion of the cold leg (outlet) side of the No. 21 steam generator. This selection was made on the basis of a prominent interbead liquid penetrant indication between the outlet nozzle and the access manway.

We are in the process of developing the inspection program such that a base line examination can be performed prior to startup of the Unit. It is our intent to perform such examinations during each of the first three refueling outages to verify that the clad crack does not propogate into the base metal.

Proposed technical specifications will be transmitted to you in the near future.

Should you have any questions in this regard, please do not hesitate to contact us.

Very truly yours,

'/(/M; R. L. Mitt*

General Manager -

Licensing and Environment Engineering and Construction O'

'0~~D 190:J-l!Ji'8 Fl ll:\RSOI' St:ll\lCE 7 9 07 2 5 (r-3°3()

95-2001 (200M) 2-78

  • UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555
50-3 /}

FILE July 18, 1979 ALL PRESSURIZED WATER REACTOR LICENSEES Gentlemen:

Enclosed is a*copy of Revision 2 of the Draft Radiological Effluent Technical Specifications, (NUREG-0472, PWR; NUREG-0473, BWR). This revision embodies corrections of errors found in previous revisions, revisions in format for consistency with Appendix 11 A11 Standard Technical Specifications, and some

  • rewriting for clarification.

If you have prepared Radiological Effluent Technical Specifications to a previous revision but have not submitted them to NRC, do not convert them fo this Revision 2 format. You should submit them in their present format since the information required for Revision 2 is available in previous revisions. Otherwise, Revision 2 should be used to prepare your Technical Specification submittal.

J In i:hose.*cases where submittals of..:Radiologl~al Effluent Technical Specifications in a previous format are made to NRC, the final specifications, after negotia-

~ions and reviews have been completed, will be based on Revision 2.

If you have any questions, please contact us.

Sincerely,

,

w.01.fr~~

William P. Garrunill, Acting Assistant Director for Operating Reactor Projects Division of Operating Reactors

Enclosure:

NUREG-0472, Revision 2

{ ,f)L io~z CJ s f'-,,___f, )

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