NUREG-1217, Forwards NRC Resolution of USI A-47, Safety Implications of Control Sys, for Info.Resolution Consists of NUREG-1217, Evaluation of Safety Implications...Technical Findings Re USI A-47 & NUREG-1218, Regulatory Analysis.... W/O Encls
| ML19325C712 | |
| Person / Time | |
|---|---|
| Issue date: | 10/04/1989 |
| From: | Rathbun D NRC OFFICE OF GOVERNMENTAL & PUBLIC AFFAIRS (GPA) |
| To: | Breaux J, Jeanne Johnston, Sharp P, Synar M, Udall M HOUSE OF REP., ENERGY & COMMERCE, HOUSE OF REP., GOVERNMENT OPERATIONS, HOUSE OF REP., INTERIOR & INSULAR AFFAIRS, SENATE, APPROPRIATIONS, SENATE, ENVIRONMENT & PUBLIC WORKS |
| References | |
| REF-GTECI-A-47, REF-GTECI-SY, RTR-NUREG-1217, RTR-NUREG-1218, TASK-A-47, TASK-OR CCS, NUDOCS 8910170204 | |
| Download: ML19325C712 (5) | |
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- o October 4, 1989 The Honorable Mike Synar, Chairman Subcomittee on Environment, Energy and Natural Resources 1
Committee on Governnient Operatioris United States House of Representatises Washington, D. C.
20515
Dear Mr. Chairmon:
Enclosed for the information of the Subcommittee on Energy eno the Environment is the NRC's resolution of Unresclved Safety Issue (USI)! A-47,
" Safety Implications of Control Systems." The resolution consists of two final reports entitled " Evaluation of Safety Intpl1cotions of Control Systems in thR Nuclear Power Plants - Technical Findings Related to USI A+47" (NUREG-1217) and "Reculatory Ar,r. lysis for Resolution of L'SI A-47" (NUREG-1218).
The proposed resolution ar.d the draft !!L' REG reports were publisbeo for public coment on May 27, 1988. All the co:urents received were addressed and are summarized in Appendix C of NUREG-1217.
USI A-47 was identified as an Unresolved Safety issue in the NRC 1980 Annual Report pursuant to Section 210 of the Energy Reorganization Act of 1974 as amended on December 13, 1977.
l
.The stoff concluded from its A-47 investigations that certain actions should be taken to f urther enhance safety in LWR plants.
These acticns recommend that plants (1) provide systerr.s to protect against reactor vessel / steam generator overfill events and to prevent steam generator dryout, (2) include in.their plant procedures and their Technical Specifications provisions to periodically verify the operability of these systems, and (3) modify selected emergency procedbres to ensure safe pler.t shutdown following a snell-break loss-nf-coolant occident.
The actions l
apply to a limited number of plarit5 for which enhanced protection is l
I warranted.
To implement this resolution, the staff will issue a generic letter tr, all LWR plants requesting thot these actions be implementec within a prescribed schedule.
Sincerely.
Otr.nis K. Rethbur, Direc or Congressiere'. Affairs Office of Ocvernr:e ve. and
'8910170204 091004 Public Aff airs POR OTECI GSYA-47 y
Enclosures:
t 1.
NUREG-1217 FULL TEXT ASCH SCAN
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2.
h0 REG-1216 3.
Federal Register t,ctice N fili m F. Clinser Jr.
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October 4. 1989 I
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i The Honorable J. Bennett Johnston, Chairman r
Subcomittee on Energy and Water Development Comittee on Appropriations United States Senate Washington, D. C.
20510 Desr Mr. Chairman:
Enclosed for the information of the Subcomittee on Energy and the Environment is the NRC's resolution of Unresolved Safety Issue (USI) A-47,
" Safety Implications of Control Systems." The resolution consists of two final reports entitled " Evaluation of Safety Implications of Control Systems in LWR Nuclear Power Plants - Technical findings Related to USI A-47" (NUREG-1217) and " Regulatory Analysis for Resolution of USI A-47" i
(NUREG-1218).
The proposed resolution and the draf t NUREG reports were published for public coment on May 27, 1988. All the coments received were addressed and are sumarized in Appendix C of NUREG-1217.
USI A-47 was identified as an Unresolved Safety Issue in the NRC 1980 Annual. Report pursuant to Section 210 of the Energy Reorganization Act of 1974 as amended on December 13, 1977.
The staff concluded from its A-47 investigations that certain actions should be taken to further enhance safety in LWR plants. These actions recomend that plants (1) provide systems to protect against reactor vessel / steam generator overfill events and to prevent steam generator dryout, (2) include in their. plant procedures and their Technical Specifications provisions to periccically verify the operability of these systems, and (3) modify selected emergency procedures to ensure safe plant The actions shutdown following a small-break loss-of-coolant accident.
t apply to a limited number of plants for which enhanced protection is warranted.
To implement this resolution, the staff will issue a generic letter to all LWR plants requesting that these actions be implemented within a l
L prescribed schedule.
Sincerely.
M Dennis K. Rathbun, Director Congressional Affairs Office of Governmental and Public Affairs
Enclosures:
1.
NUREG-1217 2.
NUREG-1218 3.
Federal Register Notice 1
cc: w/ enc 1: Sen. Mark 0. Hatfield
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A October 4, 1989 A
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The Honorable John B. Breaux, Chairman j
Subcommittee on Nuclear Regulation Comittee on Environment and Public Works United States Senate Washington, D. C.
20510
Dear Mr. Chairman:
Enclosed for the information of the Subcommittee on Energy and the Environment is the NRC's resolution of Unresolvec Safety issue (US1) A-47,
" Safety Implications of Control Systems." The resolution consists of two final reports entitled " Evaluation of Safety Implications of Control Systems in LWR Nuclear Power Plants - Technical findings Related to USI A-47" (NUREG-1217) and " Regulatory Analysis for Resolution of USI A-47" (NUREG-1218).
The proposed resolution and the draft NUREG reports were published for pubile comment on May 27, 1988. All the comments received were addressed and are sumarized in Appendix C of NUREG-1217.
USI A-47 was identifiec as an Unresolved Safety Issue in the NRC 1980 Annual Report pursuant to Section 210 of the Energy Reorganization Act of 1974 as amended on December 13, 1977.
The staff concluded from its A-47 investigations that certain actions should be taken to further enhance safety in LWR plants. These actions recommend that plants (1) provide systems to protect against reactor vessel / steam generator overfill events and to prevent steam generator dryout, (2) include in their plant procedures and their Technical Specifications provisions to periodically verify the operability of these systems, and (3) modify selected emergency procedures to ensure safe plant The actions shutdown following a small-break loss-of-coolant accident.
. apply to a limited number of plants for which enhanced protection is warranted.
To implement this resolution, the staff will issue a generic letter to all LWR plants requesting that these actions be implemented within a prescribed schedule.
Sincerely, M
Dennis K. Rathbun, Director Congressional Affairs Office of Governmental aid Public Affairs
Enclosures:
1.
NUREG-1217 2.
NUREG-1218 3.
Federal P.egister Notice cc: w/ enc 1: Sen. Alan K. Simpson
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October 4, 1989 l
The Honorable Philip R. Sharp, Chairman Subcomittee on Energy and Power Comittee on Energy and Comerce i
United States House'of Representatives Washington, D. C.
20515 F
Dear Mr. Chairman:
Enclosed for the information of the Subcommittee on Energy and the Environment is the !!RC's resolution of Unresolved Safety Issue (USI) A-47,
" Safety Implications of Control Systems." The resolution consists of two final reports entitled " Evaluation of Safety implicatiens of Control Systems in LWR Nuclear Power Plants - Technical Findings Related to USI A-47" (NUREG-1217) and " Regulatory Analysis for Resolution of US! A-47" (NUREG-1218).
The proposed resolution and the draft NUREG reports were published for public coment on May 27, 1988. All the coments received were addressed and are sumarized in Appendix C of NUREG-1217.
USI A-47 was identified as an Unresolved Safety Issue in the NRC 1980 1
Annual Report pursuant to Section 210 of the Energy Reorganization Act of 1974 as amended on December 13, 1977.
The staff concluded from its A-47 investigations that certain actions should be taken to further enhance safety in LWR plants. These actions recomend that plants (1) provide systems to protect against reactor vessel / steam generator overfill events and to prevent steam generator dryout, (2) include in their plant procedures and their Technical Specifications provisions to periodically verify the operability of'these systems, and (3) modify selected emergency procedures to ensure safe plant The actions shutdown following a small-break loss-of-coolent accident.
apply to a limited number of plants for which enhanced protection is warranted.
To implement this resolution, the staff will issue a generic letter to all LWR plants requesting that these actions be implemented within a prescribed schedule.
S incerely,
f/
Dennis K. Rathbun, Director Congressional Affairs Office of Governmental tod Public Affairs
Enclosures:
1.
fl0 REG-1217 2.
NUREG-1218 3.
Federal Register flotice cc: w/ encl: Rep. Carlos J. Moorhead
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October 4, 1989
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The Honorable Morris K. Udall, Chairman Subcomittee on Energy and the Environment Comittee on Interior and Insular Affairs
' United States Hcuse of Representatives Washington, D. C.
20515
Dear Mr. Chairman:
Enclosed for the'information of the Subcomittee on Energy and the Environment is the NRC's resolution of Unresolved Safety issue (USI) A-47, y
" Safety Implications of Control Systems." The resolution consists of two finel reports entitled "Eveluation of Safety Implications of Control Systems in LWR Nuclear Power Plants - Technical Findings Related to USI A-47" (NUREG-1217) ano " Regulatory Analysis for Resolution of USI A-47" (NUREG-1218).
The proposed resolution ano the draf t NUREG reports were published for public coment on May 27, 1988. All the comments received were addressed and are surcraarized in Appendix C of NUREG-1217.
US1 A 47 was identified as an Unresolvec Safety issue in the NRC 1980 Annual Report pursuant to Section 210 of the Energy Reorganization Act of 1974 as amended on December 13, 1977.
The staff concluded from its A-47 investigations that certain actions should be taken to further enhance safety in LWR plants. These actions recommend that plants (1) provide systerrs to protect against reactor vessel / steam generator overfill events and to prevent steam generator dryout. (2) include in their plant procedures and their Technical Specifications provisions to periodically verify the operability of these systems, and (3) modify selected emergency procedures to ensure safe plent The 6ctions shutdown following a small-break lois-of-coolant accident.
apply to a limited number of plants for which enhanced protectior is warranted.
To implement this resolution, the staff will issue a generic letter to all LWR plants requesting that these actions be implemented within a prescribed schedule.
Since rely,
Dennis K. Rathbun, Director Congressional Affairs Office of Governnental and Public Affairs
Enclosures:
1.
NUREG-1217 2.
NUREG-1218 3.
Federal Register hotice cc: w/(nc1: Rep. Jeres V. Hansen
-