ML20101J059: Difference between revisions
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s | s sp GPU Nuclear Corporation he Q | ||
sp | %[ | ||
(717) 948-8005 June 24, 1992 C311-92-2006 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Gentlemen: | Post Office Box 480 Route 441 South Middletown, Pennsylvania 170$7 0191 717 944 7621 TELEX 84 2386 Writer's Direct Otal Number: | ||
(717) 948-8005 June 24, 1992 C311-92-2006 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. | |||
20555 Gentlemen: | |||
==Subject:== | ==Subject:== | ||
| Line 29: | Line 31: | ||
Also enclosed is one signed copy of the Certificate of Service for this request certifying service to the chief executives of the township and county in which the facility is located, as well as the designated official of the Commonwealth of Pennsylvania Bureau of Radiation Protection. | Also enclosed is one signed copy of the Certificate of Service for this request certifying service to the chief executives of the township and county in which the facility is located, as well as the designated official of the Commonwealth of Pennsylvania Bureau of Radiation Protection. | ||
The attached Technical Specification Change Request (TSCR) proposes to revise the current Technical Specifications to implement a 24 month plant refueling cycle which includes an operating cycle and one refus11ng/ maintenance outage. | The attached Technical Specification Change Request (TSCR) proposes to revise the current Technical Specifications to implement a 24 month plant refueling cycle which includes an operating cycle and one refus11ng/ maintenance outage. | ||
The attachment provides justification to support the proposed TSCR. In addition, justification to support extension of each of. the affected individual refueling interval surveillances is provided. The guidance contained in NRC Generic letter 91-04, dated April 2, 1991, has been addressed where applicable. Evaluation of some equipment and system operating and surveillance histories is ongoing. Therefore, this TSCR specifically ' | The attachment provides justification to support the proposed TSCR. | ||
In addition, justification to support extension of each of. the affected individual refueling interval surveillances is provided. The guidance contained in NRC Generic letter 91-04, dated April 2, 1991, has been addressed where applicable. Evaluation of some equipment and system operating and surveillance histories is ongoing. | |||
Therefore, this TSCR specifically ' | |||
addresses those Technical Specification revisions and equipment or system surveillance extensions for which an eval'uation has been completed to date. | addresses those Technical Specification revisions and equipment or system surveillance extensions for which an eval'uation has been completed to date. | ||
$e Extension of the OTSG inspection surveillance interval is not being proposed g | |||
at this time. | |||
00 | 00 | ||
@$l This TSCR proposes to maintain the current specified surveillance interval for 00 equipment and systems which have not yet been evaluated. This will allow cs:c issuance of an amendment extending those surveillances justified herein, M | |||
including the refueling interval definition, while maintaining the current oc interval for the surveillances currently under review. An additional TSCR P | |||
will be submitted for the remaining affected equipment and systems requesting | |||
g | @g surveillance extensions necessary to accommodate full implementation of the 24 | ||
/ | |||
g month plant cycle. These additional surveillances can be performed during g/ | |||
_ plant operation. | _ plant operation. | ||
3 0 0 0 C .2 | 3 0 0 0 C.2 GPU Nuclear Corporahon is a subsidiary of Generat Public Ubbties Corporabon | ||
j. | j. | ||
p- | p-Document Control Des' C311-92-2006 j | ||
Page_2 4 | |||
It is intended that the first 24 month cycle will commence with the 10R l | |||
-refueling / maintenance outage planned for September 1993. | |||
Pursuant- to 10 CFR 50.91(a)(1), enclo' sed is :an analysis-applying the standards i | Pursuant-to 10 CFR 50.91(a)(1), enclo' sed is :an analysis-applying the standards i | ||
in 10 CFR 50.92 to make a determination of no significant hazards-considerations. As stated above, pursuant to 10 CFR 50.91(a) of the i | |||
regulations, we have provided a copy of this letter, the proposed change in i-Technical Specifications, and our analyses of sig'11ficant hazards j | |||
considerations to William P. Dornsife, the designated representative of the commonwealth of Pennsylvania. | |||
Sincerely, i-l | |||
' fUv.dW T.G.Brouhiton j | |||
_Vice_ President and Director,-THI-l DJD/amk | |||
==Enclosures:== | ==Enclosures:== | ||
(1) | (1) | ||
[- | Technical Specification Change ' Request No. 206 j-(2) | ||
Certificate of Service for Technical Specification-Change Request No. 206 k | |||
i i-cc: Administrator, Region I i | |||
TMI Senior Resident Inspector | |||
[- | |||
THI-1 Senior Project Manager | |||
-l 1}} | |||
Latest revision as of 04:44, 13 December 2024
| ML20101J059 | |
| Person / Time | |
|---|---|
| Site: | Crane |
| Issue date: | 06/24/1992 |
| From: | Broughton T GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20101J062 | List: |
| References | |
| C311-92-2006, GL-91-04, GL-91-4, NUDOCS 9206300322 | |
| Download: ML20101J059 (2) | |
Text
-
s sp GPU Nuclear Corporation he Q
%[
Post Office Box 480 Route 441 South Middletown, Pennsylvania 170$7 0191 717 944 7621 TELEX 84 2386 Writer's Direct Otal Number:
(717) 948-8005 June 24, 1992 C311-92-2006 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C.
20555 Gentlemen:
Subject:
Three Mile Island Nuclear Station, Unit 1 (THI-1)
Docket No. 50-289 Operating License No. DPR-50 Technical Specification Change Request No. 206 24 Month Cycle Surveillance Extensions In accordance with 10 CFR 50.4(b)(1), enclosed is Technical Specification Change Request No. 206.
Also enclosed is one signed copy of the Certificate of Service for this request certifying service to the chief executives of the township and county in which the facility is located, as well as the designated official of the Commonwealth of Pennsylvania Bureau of Radiation Protection.
The attached Technical Specification Change Request (TSCR) proposes to revise the current Technical Specifications to implement a 24 month plant refueling cycle which includes an operating cycle and one refus11ng/ maintenance outage.
The attachment provides justification to support the proposed TSCR.
In addition, justification to support extension of each of. the affected individual refueling interval surveillances is provided. The guidance contained in NRC Generic letter 91-04, dated April 2, 1991, has been addressed where applicable. Evaluation of some equipment and system operating and surveillance histories is ongoing.
Therefore, this TSCR specifically '
addresses those Technical Specification revisions and equipment or system surveillance extensions for which an eval'uation has been completed to date.
$e Extension of the OTSG inspection surveillance interval is not being proposed g
at this time.
00
@$l This TSCR proposes to maintain the current specified surveillance interval for 00 equipment and systems which have not yet been evaluated. This will allow cs:c issuance of an amendment extending those surveillances justified herein, M
including the refueling interval definition, while maintaining the current oc interval for the surveillances currently under review. An additional TSCR P
will be submitted for the remaining affected equipment and systems requesting
@g surveillance extensions necessary to accommodate full implementation of the 24
/
g month plant cycle. These additional surveillances can be performed during g/
_ plant operation.
3 0 0 0 C.2 GPU Nuclear Corporahon is a subsidiary of Generat Public Ubbties Corporabon
j.
p-Document Control Des' C311-92-2006 j
Page_2 4
It is intended that the first 24 month cycle will commence with the 10R l
-refueling / maintenance outage planned for September 1993.
Pursuant-to 10 CFR 50.91(a)(1), enclo' sed is :an analysis-applying the standards i
in 10 CFR 50.92 to make a determination of no significant hazards-considerations. As stated above, pursuant to 10 CFR 50.91(a) of the i
regulations, we have provided a copy of this letter, the proposed change in i-Technical Specifications, and our analyses of sig'11ficant hazards j
considerations to William P. Dornsife, the designated representative of the commonwealth of Pennsylvania.
Sincerely, i-l
' fUv.dW T.G.Brouhiton j
_Vice_ President and Director,-THI-l DJD/amk
Enclosures:
(1)
Technical Specification Change ' Request No. 206 j-(2)
Certificate of Service for Technical Specification-Change Request No. 206 k
i i-cc: Administrator, Region I i
TMI Senior Resident Inspector
[-
THI-1 Senior Project Manager
-l 1