Letter Sequence Other |
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MONTHYEARML19317H3061980-04-10010 April 1980
Model Tech Specs for PWRs & BWRs
Project stage: Other
ML19317H3041980-04-10010 April 1980
Forwards Model Tech Specs for PWRs & Bwrs.Requests That Utils Submit Proposed Changes to Tech Specs,Incorporating Encl Requirements,Within 30 Days & Implementing Described Procedures for Compliance within 30 Days Thereafter
Project stage: Other
IR 05000266/19800091980-05-16016 May 1980
IE Insp Repts 50-266/80-09 & 50-301/80-08 on 800310-14 & 0408.No Noncompliance Noted.Major Areas Inspected:Plant Procedures & Operator Training.On 800408 Meeting Was Held to Review Plant Performance
Project stage: Request
A800028, Responds to NRC Requesting Amend to Radiological Tech Specs to Clarify Meaning of Term Operable.Previous Discussions W/Ie Inspector Concluded Spec Contains Adequate Clarification & No Addl Revision Is Necessary1980-05-30030 May 1980
Responds to NRC Requesting Amend to Radiological Tech Specs to Clarify Meaning of Term Operable.Previous Discussions W/Ie Inspector Concluded Spec Contains Adequate Clarification & No Addl Revision Is Necessary
Project stage: Other
ML19332B0891980-09-19019 September 1980
Application to Amend Licenses DPR-24 & DPR-27,changing Tech Specs 15.1,15.3 & 15.6,re Limiting Conditions for Operations,Definitions of Operability & Administrative Structure
Project stage: Request
ML19332B0911980-09-19019 September 1980
Tech Spec Change Request 64,consisting of Proposed Tech Specs 15.1,15.3 & 15.6 Re Limiting Conditions for Operations,Definition of Operability & Administrative Structure
Project stage: Other
ML19339C4741980-11-14014 November 1980
Discusses License Amend Approval Fees.Only Single Class 1 Duplicate Amend Fee Appropriate Since All Amend Changes Have Been Provided & Should Be Processed & Issued at Same Time
Project stage: Other
ML19340E9871981-01-13013 January 1981
Responds to NRC 801219 Request for Second Class I License Amend Approval Fee for 800919 Tech Spec Change Request 64. No Addl Administrative Effort Required for Issuance of Tech Spec Pages for Second Unit
Project stage: Request
ML20005A7271981-06-24024 June 1981
Notice of Issuance & Availability of Amends 50 & 56 to Licenses DPR-24 & DPR-27,respectively
Project stage: Other
ML20005A7241981-06-24024 June 1981
Amends 50 & 56 to Licenses DPR-24 & DPR-27,respectively, Revising Definition of Operability & Adding New Specs to Address Limiting Conditions for Operation & Inoperability of safety-related Sys Due to Loss of Power Supply
Project stage: Other
ML20009A7761981-07-0606 July 1981
Corrected Tech Spec Page 15.6.11-1 for Amends 50 & 54 to Licenses DPR-24 & DPR-27,respectively
Project stage: Other
1980-05-30
[Table View] |
Forwards Model Tech Specs for PWRs & Bwrs.Requests That Utils Submit Proposed Changes to Tech Specs,Incorporating Encl Requirements,Within 30 Days & Implementing Described Procedures for Compliance within 30 Days Thereafter| ML19317H304 |
| Person / Time |
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| Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Nine Mile Point, Palisades, Indian Point, Kewaunee, Saint Lucie, Point Beach, Oyster Creek, Cooper, Pilgrim, Arkansas Nuclear, Prairie Island, Brunswick, Surry, North Anna, Turkey Point, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Duane Arnold, Farley, Robinson, San Onofre, Cook, Yankee Rowe, Maine Yankee, Quad Cities, La Crosse, Big Rock Point, Rancho Seco, Zion, Fort Calhoun, FitzPatrick, Fort Saint Vrain, Trojan, Crane  |
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| Issue date: |
04/10/1980 |
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| From: |
Eisenhut D
Office of Nuclear Reactor Regulation |
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| To: |
Andognini G, Arnold D, Bauer E, Berry G, Cavanaugh W, Counsil W, Dietch R, Dise D, Finfrock I, Hoffman D, Jackie Jones, Kay J, Linder F, Mayer L, Parris H, Peoples D, Pilant J, Roe L, Rich Smith, White L, Whitmer C
ALABAMA POWER CO., ARKANSAS POWER & LIGHT CO., BALTIMORE GAS & ELECTRIC CO., BOSTON EDISON CO., CAROLINA POWER & LIGHT CO., COMMONWEALTH EDISON CO., CONNECTICUT YANKEE ATOMIC POWER CO., CONSOLIDATED EDISON CO. OF NEW YORK, INC., CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.), DAIRYLAND POWER COOPERATIVE, DUKE POWER CO., DUQUESNE LIGHT CO., FLORIDA POWER & LIGHT CO., FLORIDA POWER CORP., GEORGIA POWER CO., IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT, INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG, JERSEY CENTRAL POWER & LIGHT CO., Maine Yankee, METROPOLITAN EDISON CO., NEBRASKA PUBLIC POWER DISTRICT, NIAGARA MOHAWK POWER CORP., NORTHEAST NUCLEAR ENERGY CO., NORTHERN STATES POWER CO., OMAHA PUBLIC POWER DISTRICT, PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC, PORTLAND GENERAL ELECTRIC CO., POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK, PUBLIC SERVICE CO. OF COLORADO, Public Service Enterprise Group, ROCHESTER GAS & ELECTRIC CORP., SACRAMENTO MUNICIPAL UTILITY DISTRICT, SOUTHERN CALIFORNIA EDISON CO., TENNESSEE VALLEY AUTHORITY, TOLEDO EDISON CO., VERMONT YANKEE NUCLEAR POWER CORP., VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.), WISCONSIN ELECTRIC POWER CO., WISCONSIN MICHIGAN POWER CO., WISCONSIN PUBLIC SERVICE CORP., YANKEE ATOMIC ELECTRIC CO. |
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| Shared Package |
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| ML19317H305 |
List: |
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| References |
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| TASK-16, TASK-RR TAC-13210, TAC-43031, TAC-43032, NUDOCS 8005190009 |
| Download: ML19317H304 (5) |
|
Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Nine Mile Point, Palisades, Indian Point, Kewaunee, Saint Lucie, Point Beach, Oyster Creek, Cooper, Pilgrim, Arkansas Nuclear, Prairie Island, Brunswick, Surry, North Anna, Turkey Point, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Duane Arnold, Farley, Robinson, San Onofre, Cook, Yankee Rowe, Maine Yankee, Quad Cities, La Crosse, Big Rock Point, Rancho Seco, Zion, Fort Calhoun, FitzPatrick, Fort Saint Vrain, Trojan, Crane |
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Category:CORRESPONDENCE-LETTERS
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Indian Point]] OR [[:Kewaunee]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Cooper]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Prairie Island]] OR [[:Brunswick]] OR [[:Surry]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:Fort Saint Vrain]] OR [[:Trojan]] OR [[:Crane]] </code>.
Category:OUTGOING CORRESPONDENCE
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Indian Point]] OR [[:Kewaunee]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Cooper]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Prairie Island]] OR [[:Brunswick]] OR [[:Surry]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:Fort Saint Vrain]] OR [[:Trojan]] OR [[:Crane]] </code>. |
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8006190009 T/M ALL POWER REACTOR LICEriSEES Docket flo. 50-348 Docket flo. 50-3 Farley Unit 1 Indian Point Unit 1 Docket flo. 50-313 Docket flo. 50-247 Arkansas Unit 1 Indian Point Unit 2 Docket flo. 50-368 Docket 50-286 Arkansas Unit 2 Indian Point Unit 3 Docket rio. 50-317 Docket flo. 50 155 Calvert Cliffs Unit 1 Big Rock Point Docket No. 50-318 Docket flo. 50-255 Calvert Cliffs Unit 2 Palisades Docket No. 50-293 Docket No. 50-409 Pilgrim Unit 1 Lacrosse Docket flo. 50-325 Docket tio. 50-269 Brunswick Unit 1 Oconee Unit 1 Docket l10. 50-324 Docket flo. 50-270 Brunswick Unit 2 Oconee Unit 2 Docket flo. 50-261 Docket flo. 50-287 H. B. Robinson Unit 2 Oconee Unit 3
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Docket flo. 50-10 Docket No. 50-334 Dresden Unit 1 Beaver Valley Unit 1 Docket flo. 50-237 Docket flo. 50-302 Dresden Unit 2 Crystal River 3 Docket !Io. 50-249 Docket flo. 50-335 Dresden Unit 3 St. Lucie Unit 1 Docket lio. 50-254 Docke-tio. 50-250 Quad-Cities Unit 1 Turkey Point Unit 3 Docket !!o. 50-265 Docket ilo. 50-251 Quad-Cities Unit 2 Turkey Point Unit 4 Docket flo. 50-295 Docket tio. 50-321 Zion Unit 1 Edwin 1. Hatch Unit 1 Docket flo. 50-304 Docket No. 50-366 Zion Unit 2 Edwin I. Hatch Unit 2 Docket No. 50-213 Docket No. 50-315 Connecticut Yankee (Haddam lleck)
D. C. Cook Unit 1
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. i Docket No. 50-316 Docket No. 50-344 D. C. Cook Unit 2 Trojan Docket No. 50-331 Docket No. 50-333 Duane Arnold FitzPatrick Docket No. 50-219 Docket No. 50-267 Oyster Cree,k Unit 1 Ft. St. Vrain Docket No.[50-309 Docket No. 50-272 l
MaineYankde Salem Unit i Docket No. 50-289 Docket No. 50-244 Three Mile Island Unit 1 R. E. Ginna 1 Docket flo. 50-320 Docket No. 50-312 Three Mile Island Unit 2 Rancho Seco 4
Docket No. 50-298 Docket No. 50-206 Cooper Station San Onofre 1 Docket No. 50-220 Docket No. 50-259 Nine Mile Point Unit 1 Browns Ferry Unit 1 Docket flo. 50-245 Docket No. 50-260 Millstone Unit 1 Browns Ferry Unit 2 Docket flo. 50-336 Docket No. 50-296 flillstone Unit 2 Browns Ferry Unit 3 Docket No. 50-263 Docket No. 50-346 Monticello Davis-Resse 1 Docket No. 50-282 Docket No. 50-271 Prairie Island Unit i Vermont Yankee i
Docket No. 50-306 Docket No. 50-338 1-Prairie Island Unit 2 North Anna 1 Docket flo. 50-285 Docket No. 50-280 ft. Calhoun Surry 'anit 1
-@rw+et-41a-.40 133-Docket No. 50-281 "stidt by Surry Unit 2 Docket No. 50-277 Docket No. 50-266 Peach Bottom 2 Point Beach Unit 1
-Docket No. 50-278' Docket No. 50-301 Peach Bottom 3 Point Beach Unit 2
. Docket flo. 50-305 Kewaunee Docket flo. 50-29 Yankee-Rowe i
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION 3
C WASHING TON, D. C. 20565 9,
I April 10, 1980 ALL POWER REACTOR LICENSEES ( h ce d b b M c N l)
Gentlemen:
It has recently come to our attention that there may be some misunderstanding regarding the use of the term OPERABLE as it applies to the single failure criterion for safety systems in power reactors. The purpose of this letter is to clarify the meaning of this term and to request licensees to take specific actions to assure that it is appropriately applied at their facilities.
IE Information Notice No. 79-35, " Control of Maintenance and Essential Equipment" dlso Contained information on this stubject.
The NRC's Standard Technical Specifications (STS) were fonnulated to preserve the single failure criterion for systems that are relied upon in the safety analysis report.
By and large, the single failure criterion is preserved by specifying Limiting Conditions for Operation (LCOs) that require all redundant components of safety related systems to be OPERABLE. When the required' redundancy is not maintained, either due to equipment failure or maintenance outar e, action is required, within a specified time, to change the operating mode >f the plant to place it in a safe condition. The specified time to take action, usually called the equipment out-of-service time, is a temporary relaxation of the single failure criterion, which, consistent with overall system reliability considerations, provides a limited time to fix equipment or otherwise make it OPERABLE.
If equipment can be returned to OPERABLE status within the specified time, plant shutdown is not required.
LCOs are specified for each safety related system in the plant, and with few exceptions, the ACTION statements address single outages of components, train:
or subsystems.
For any particular system, the LC0 does not address multiple outages of redundant components, nor does it address the effects of outages of any support systems - such as electrical power or cooling water - that are relied upon to maintain the OPERABILITY of the particular system. This is because of the large number of combinations of these types of outages that are possible.
Instead, the STS employ general specifications and an explicit definition of the term OPERABLE to encompass all such cases. These provisions have been formulated to assure that no set o.f equipment outages would be allowed to persist that would result in the facility being in an unprotected condition. These specifications are contained in the enclosed Model Technical Specifica tions.
Illustrative examples of how these specifications apply are contained in the associated Bases.
. April 10, 1980 Because of the importance of assuring safety system availability, the staff has concluded that all facility technical specifications should contain these requirements, and that appropriate procedures should be implemented to assure that the necessary records, such as plant logs or similar documents, are reviewed to detennine compliance with these specifications (1) promptly upon discovering a component, train, or subsystem to La inoperable, and (2) prior to removing a component from service.
Therefore, we request that you (1) submit proposed changes to your technical specifications, within 30 days, that incorporate the requirements of the enclosed Model Technical Specifications, and (2) implement the above described procedures to assure compliance with your proposed changes within 30 days thereafter.
With i-egard to technical specification changes, we recognize that the terminology used in the enclosed Model Technical Specifications may not directly apply to plants witnout STS, therefore the OPERATIONAL MODE or C0dDITION definitions are also included in the enclosure.
If you do not have STS you should modify the terminology to make it consistent with your particular facility technical specifications.
If you have any questions, please contact us.
Sincerely, anL O.
M DarrellG.Elsenhut, Acting Director Division of Operating Reactors Office of Nuclear Reactor Regulation
Enclosure:
Model Technical Specifications
_