ML19270H562
| ML19270H562 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/27/1978 |
| From: | Grimes B, Stello V Office of Nuclear Reactor Regulation |
| To: | Herbein J METROPOLITAN EDISON CO. |
| Shared Package | |
| ML19270H563 | List: |
| References | |
| RTR-REGGD-01.083, RTR-REGGD-1.083 NUDOCS 7911110078 | |
| Download: ML19270H562 (4) | |
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DISTRIBUTION:
June 27,1978 mor.kat-NRC PDR L PDR ORB #4 Reading Docket No. 50-289 VStello KRGoller ACRS(16)
RIngram OPA, Clare Miles GZwetzig Dross LShao TAbernathy Metropolitan Edison Co:ncany OELD JBuchanan ATTH: Mr. J. G. Herbein 0I&E(5) file Vice President BJones(4)
XTRA (4)
- p. D. Box 542 BScharf(15)
Reading, Pennsylvania 19603 JMcGough EHarless Gentlemen:
DEisenhut By letter dated October 17, 1974, we' requested that you propose suitable Technical Specifications for Three Mile Island Nuclear Generating Station, Unit No.1 (TMI-1) for the surveillance of steam generator tubes consistent with the requirtments of the General Design Criteria and Regulatory Guide 1.83, " Inservice Inspection of Pressurized Water Reactor Steam Generator Tubes." In your response, dated November 29,1974 you listed reasons why you believed the Babcock & W O cox once-through-steam generators at THI-1 should not be subject to these requirements.
In our letter of September 14, 1976, we advised you that there was as yet insufficient long tem operating experience with Babcock &
Wilcox once-through steam generators to justify not pedorming these inspections. In this letter we again requested that yea submit,an application for amendnent of the license for THI-1 to provide technical specifications for steam generator surveillance. We also supplied model technical specifications to assist you in preparing your submittal.
By. letter dated November 12. 1976, you transmitted a preposed amendment to the THI-1 Technical Specifications which was not fully responsive to the guidance contained in the model technical specifications.
Accordingly, by 4etter dated December.14,1976, we asked that you resubmit tb request #or amendment in a form consistent with the
. guidance we had provided and, if there were conditions unique to TMI-1 that necessitated exceptions to the guidance, we requested that you provide specific justification for such exceptions.
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Your resubmittal of January 7,1977, wtile conforming mre closely to the model technical specifications, still retained certain vital exceptions which were not adequately justified. These matters have been discussed with you and your staff, and a number of differences have been satisfactorily resolved. You have verbally indicated, however, that you still do not agree with the need for certain provisions of the model technical specifications which we consider essential.
Because of the potential adverse effects on public health and safety which could result from an accident while operating with a significant number of steam generator tubes either leaking or susceptible to accident-induced leakage, we believe that appmpriate changes to the TMI-1 Technical Specifications are needed to assure a high degree of steam generator tube integrity. The basis for this position is provided in our Safety Evaluation, a copy of which is enclosed. Accordingly, unless you infom us in writing within 20 days of the date of this letter that you do not agree with this course of action, including your reasons, we plan to initiate steps to isst:e the enclosed change to the Technical Specifications for TMI-1.
Sincerely, Brian L Grimes Assistant Director for Engineering & Projects Division of Operating Reactors
Enclosures:
1.
Proposed Changes to Technical Specifiestians 2.
Safet;y Evaluation o?o1
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-e-Your resubmittal of January 7,1977. while conforming more closely to the model technical specifications, still retained certain vital exceptions which were not adequately justified. These matters have been discussed with you and your staff, and a number of differences have been satisfactorily resolved. You have verbally indicated, however, that you still do not agree with the need for certain provistens of the model technical specifications which we consider essential.
Because of the potential adverse effects on public health and safety which could result from an accident while operating with a significant nutter of steam generator tubes either leaking or susceptible to accident-induced leakage, we believe that appropriate changes to the T?il-1 Technical Specifications are needed to assure a high degree cf steam generator tube integrity. The basis for this position is provided in our Safety Evaluation, a copy of which is enclosed. Accordingly, unless you infonn us in writing within 20 days of the date of this letter
'that you do not agree with this course of action, including your reasons, we plan to initiate steps to issue the enclosed change to
.the Technical Specifications for THI-1.
Sincerely.
V. Stello, Jr., Acting Assistant Director for Operating Reactors Division of Operating Reactors v
Enclosures:
1._ Proposed Changes to Technical Specifications 2.
Safety Evaluation
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G. F. Trcr.<a ri dge, Es qui re Shaw, Pittran, Potts 6 Troworidge 1800 !! Street, !!.'.!.
!!ashington, D.C.
20036 GPU Service Corporation Richard U. Heward, Proj ect fianager fir. T. Gary Broennton. Safety and Licensing : tanager 250 Cherry itili ~,oao Parsippcny, l'eu der:c; 07054 Pennsylv;nia Electric C '~pany lir. R. 1l. C o nrr.d Vice President, G.?ncration 1001 Brcac Stract Johnstvia, Pcr.nsylvati'i 159Ti 1"i s s f u r y V.
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Citizens for a S672 On irornen P. O. Box 405 llarrisburg, Pennsylv:nia 17108 Gnvaronent Publica' ion Section State Libr ry of PenrT>lvania Box 1601 (Education Building) liarri sburg, Pennsylvraia 17126 o7oq q r 7, a..
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