ML20245L607: Difference between revisions

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=Text=
=Text=
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* jv# *''4,o,,                              UNITED STATES 8             o              NUCLEAR REGULATORY COMMISSION
* UNITED STATES j
                        $              ,I           ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, D. C. 20555 O*-
8 NUCLEAR REGULATORY COMMISSION o
                                    /g August 15, t989 Mr. James M. Taylor, Acting Executive Director for Operations
,I ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, D. C. 20555 O*-
              ~
/g August 15, t989
U.S. Nuclear Regulatory Commission Washington, D.C. 20555 L
~
l                            
Mr. James M. Taylor, Acting Executive Director for Operations U.S. Nuclear Regulatory Commission Washington, D.C.
20555 L
l


==Dear Mr. Taylor:==
==Dear Mr. Taylor:==
==SUBJECT:==
==SUBJECT:==
PROPOSED RESOLUTION OF GENERIC ISSUE 79, UNANALYZED REACTOR VESSEL (PWR) THERMAL STRESS DURING NATURAL CONVECTION C00LDOWN During the 352nd meeting of the Advisory Committee on Reactor Safe-guards, August 10-11, 1989, we met with representatives of the NRC staff
PROPOSED RESOLUTION OF GENERIC ISSUE 79, UNANALYZED REACTOR VESSEL (PWR) THERMAL STRESS DURING NATURAL CONVECTION C00LDOWN During the 352nd meeting of the Advisory Committee on Reactor Safe-guards, August 10-11, 1989, we met with representatives of the NRC staff and discussed the actions proposed by the staff for resolving Generic Issue 79.
                -            and discussed the actions proposed by the staff for resolving Generic Issue 79.
The evaluations performed within the framework of Generic Issue 79 have resolved the natural circulation cooldown (NCC) for Babcock & Wilcox nuclear steam supply systems (NSSS).
The evaluations performed within the framework of Generic Issue 79 have resolved the natural circulation cooldown (NCC) for Babcock & Wilcox nuclear steam supply systems (NSSS). The NCC condition has not been specifically evaluated for Westinghouse and Combustion Engineering PWRs.
The NCC condition has not been specifically evaluated for Westinghouse and Combustion Engineering PWRs.
However, the RES staff will recommend to NRR that if a licensee with Westinghouse or Combustion Engineering NSSS experiences a significant NCC event, the licensee should be required to provide confirmation that no applicable regulatory design or fracture toughness criteria has been l
However, the RES staff will recommend to NRR that if a licensee with Westinghouse or Combustion Engineering NSSS experiences a significant NCC event, the licensee should be required to provide confirmation that no applicable regulatory design or fracture toughness criteria has been l
e exceeded for the reactor vessel.
exceeded for the reactor vessel.
t Our only recommendation with respect to the resolution of this generic issue is that licensees with Westinghouse and Combustion Engineering
e t
  }
Our only recommendation with respect to the resolution of this generic
  '                            NSSS should be informed of this potential evaluation requirement.
}
issue is that licensees with Westinghouse and Combustion Engineering NSSS should be informed of this potential evaluation requirement.
i Sincerely, Forrest J. Remick Chairman
i Sincerely, Forrest J. Remick Chairman


==Reference:==
==Reference:==
Memorandum dated July 7, 1989 from R. W. Houston, RES, for R. F. Fraley, ACRS,  
Memorandum dated July 7, 1989 from R. W. Houston, RES, for R. F. Fraley, ACRS,  


==Subject:==
==Subject:==
Resolution of Generic Issue 79, Unanalyzed Reactor Vessel.(PWR) Thermal Stress During Natural Convection Cooldown
Resolution of Generic Issue 79, Unanalyzed Reactor Vessel.(PWR) Thermal Stress During Natural Convection Cooldown 1
                  -                          -                                                        1


a g
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s>D REGO j
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k o UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555
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WASHINGTON, D. C. 20555 j
EDO Principal Correspondence Control
[
[
DUE: 08/30/89                           EDO CONTROL: 0004677 FROM:                                                                        DOC DT: 08/15/89 FINAL REPLY:
EDO Principal Correspondence Control FROM:
DUE: 08/30/89 EDO CONTROL: 0004677 DOC DT: 08/15/89 FINAL REPLY:
Forrest J. Remick ACRS TO:
Forrest J. Remick ACRS TO:
Jan es Taylor l
Jan es Taylor l
FOR SIGNATURE OF:               ** GRN     **                              CRC NO:
FOR SIGNATURE OF:
1 Executive Director                                                                                 l DESC:                                                                      ROUTING:
** GRN CRC NO:
PROPOSED RESOLUTION OF GENERIC ISSUE 79,                                   Taylor UNANALYZED REACTOR VESSEL (PWR) THERMAL STRESS                             Thompson DURING NATURAL CONVECTION COOLDOWN                                         Blaha Murley, NRR             ;
1 l
DATE: 08/16/89                                                               Bernero, NMSS Jordan, AEOD ASSIGNED TO:             CONTACT:                                           Scinto, OGC Beckjord RES                                                  (CFiles SPECIAL INSTRUCTIONS OR REMARKS:
Executive Director ROUTING:
DESC:
PROPOSED RESOLUTION OF GENERIC ISSUE 79, Taylor UNANALYZED REACTOR VESSEL (PWR) THERMAL STRESS Thompson DURING NATURAL CONVECTION COOLDOWN Blaha Murley, NRR DATE: 08/16/89 Bernero, NMSS Jordan, AEOD ASSIGNED TO:
CONTACT:
Scinto, OGC RES Beckjord (CFiles SPECIAL INSTRUCTIONS OR REMARKS:
PREPARE RESPONSE TO ACRS FOR EDO SIGNATURE.
PREPARE RESPONSE TO ACRS FOR EDO SIGNATURE.
PUT COMMISSIONERS AND SECY ON CC (SHOWN ON ORIGINAL) FOR REPLY.
PUT COMMISSIONERS AND SECY ON CC (SHOWN ON ORIGINAL) FOR REPLY.
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Latest revision as of 00:41, 2 December 2024

Discusses Proposed Resolution of Generic Issue 79, Unanalyzed Reactor Vessel (PWR) Thermal Stress During Natural Convection Cooldown, Per ACRS 352nd Meeting on 890810-11
ML20245L607
Person / Time
Issue date: 08/15/1989
From: Remick F
Advisory Committee on Reactor Safeguards
To: Taylor J
NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
References
REF-GTECI-079, REF-GTECI-NI, TASK-079, TASK-79, TASK-OR ACRS-R-1368, NUDOCS 8908220192
Download: ML20245L607 (1)
v • d • e


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8 NUCLEAR REGULATORY COMMISSION o

,I ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, D. C. 20555 O*-

/g August 15, t989

~

Mr. James M. Taylor, Acting Executive Director for Operations U.S. Nuclear Regulatory Commission Washington, D.C.

20555 L

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Dear Mr. Taylor:

SUBJECT:

PROPOSED RESOLUTION OF GENERIC ISSUE 79, UNANALYZED REACTOR VESSEL (PWR) THERMAL STRESS DURING NATURAL CONVECTION C00LDOWN During the 352nd meeting of the Advisory Committee on Reactor Safe-guards, August 10-11, 1989, we met with representatives of the NRC staff and discussed the actions proposed by the staff for resolving Generic Issue 79.

The evaluations performed within the framework of Generic Issue 79 have resolved the natural circulation cooldown (NCC) for Babcock & Wilcox nuclear steam supply systems (NSSS).

The NCC condition has not been specifically evaluated for Westinghouse and Combustion Engineering PWRs.

However, the RES staff will recommend to NRR that if a licensee with Westinghouse or Combustion Engineering NSSS experiences a significant NCC event, the licensee should be required to provide confirmation that no applicable regulatory design or fracture toughness criteria has been l

exceeded for the reactor vessel.

e t

Our only recommendation with respect to the resolution of this generic

}

issue is that licensees with Westinghouse and Combustion Engineering NSSS should be informed of this potential evaluation requirement.

i Sincerely, Forrest J. Remick Chairman

Reference:

Memorandum dated July 7, 1989 from R. W. Houston, RES, for R. F. Fraley, ACRS,

Subject:

Resolution of Generic Issue 79, Unanalyzed Reactor Vessel.(PWR) Thermal Stress During Natural Convection Cooldown 1

a g

s>D REGO f*"

k UNITED STATES j

jg NUCLEAR REGULATORY COMMISSION o

WASHINGTON, D. C. 20555 j

[

EDO Principal Correspondence Control FROM:

DUE: 08/30/89 EDO CONTROL: 0004677 DOC DT: 08/15/89 FINAL REPLY:

Forrest J. Remick ACRS TO:

Jan es Taylor l

FOR SIGNATURE OF:

1 l

Executive Director ROUTING:

DESC:

PROPOSED RESOLUTION OF GENERIC ISSUE 79, Taylor UNANALYZED REACTOR VESSEL (PWR) THERMAL STRESS Thompson DURING NATURAL CONVECTION COOLDOWN Blaha Murley, NRR DATE: 08/16/89 Bernero, NMSS Jordan, AEOD ASSIGNED TO:

CONTACT:

Scinto, OGC RES Beckjord (CFiles SPECIAL INSTRUCTIONS OR REMARKS:

PREPARE RESPONSE TO ACRS FOR EDO SIGNATURE.

PUT COMMISSIONERS AND SECY ON CC (SHOWN ON ORIGINAL) FOR REPLY.

bylplW,5

& f w>

p M(v,, s i

'[~

NI10 RLE CENTE!1 COPY

- _ _ _ _ _ _ _

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