ML20129B897: Difference between revisions

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#REDIRECT [[IA-85-128, Discusses Effects of Fire Protection Sys Actuation on safety-related Equipment.Issue May Not Have Been Adequately Considered.Div of Engineering Reviewing Recent Fire Sys Actuations]]
{{Adams
| number = ML20129B897
| issue date = 08/27/1982
| title = Discusses Effects of Fire Protection Sys Actuation on safety-related Equipment.Issue May Not Have Been Adequately Considered.Div of Engineering Reviewing Recent Fire Sys Actuations
| author name = Denton H
| author affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| addressee name = Michelson C
| addressee affiliation = NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD)
| docket =
| license number =
| contact person =
| case reference number = FOIA-85-128
| document report number = NUDOCS 8506050357
| package number = ML20129B878
| document type = INTERNAL OR EXTERNAL MEMORANDUM, MEMORANDUMS-CORRESPONDENCE
| page count = 1
}}
 
=Text=
{{#Wiki_filter:- - -
    .. < r .'
Central Files                  DEisenhut ORAB Rdg                      GHolahan HDenton                        DPickett ECase                          SCavanaugh PPAS                            (NRR-82-306 '
SHanauer                      DNottingham RMattson                        (NRR-82-306 '
RVollmer EMORANDUM FOR: Carlyle Michelson, Director                                                      HThompson Office for Analysis and Evaluation                                  PCheck of Operational Data                                              BRnvder 6LEergusoD FROM:                        Harold R. Denton, Director                                          VBenaroya Office of Nuclear Reactor Regulation                                MChirmal, AE00 SUB_ JECT:                  EFFECTS OF FIRE PROTECTION SYSTEM ACTUATION ON SAFETY-RELATED EQUIPMENT As discussed in the AEOD memorandum on the above subject dated Janaury 28, 1932, recent operating reactor events show that s'afety-related equipment subjected to water spray from fire protection systems can be rendered                                                                                        l inoperable. The events also indicate that spurious actuation of fire protection systems can be initiated by operator error, steam flow, high humidity or maintenance activities in the vicinity of fire protection system detectors. These events tend to show that the interactions between fire protect. ion systems and other systems that affect.the operation of safety-related systems may not have been adequately considered.
The AE00 memorandum of July 28,1982, " Carbon Dioxide Systems Used for Fire Protection In or Adjacent to Critical Areas," discusses the inadver-
                  ' tent actuation of the CO2 system in the Grand Gulf ECCS penetration room.
The CO2 system overpressurized the penetration room and consequently forced ppen the locked door 'to'the auxiliary building. In addition to the event description, a number of questions relating to carbon dioxide fire protec-tion systems were raised. We consider the Grand Gulf event to be an extension of the original concem.
GDC 3 states, inppart "Firefighting systems shall be designed to assure that their rupture and inadvertent operation does not significantly impair the safety capability of these structures, systems, and components." Branch Technical Position CMEB 9.5-1 to BTP 9.5.1 has additional functional criteria for CO2 systems. During the Operating Reactor Event meeting of January 7, 1982 the Division of Engineering was assigned to review the recent fire system actuations and consider the need for modifications to requirements; or reviews. The DE study is ongoing and will consider the AEOD concern for a11 ' types of fire protection systems (e.g., water, halides, carbon dioxide and other chemicals).
We will inform you of any recommendations that may result from this study.
Additional information may be obtained from the Chemical Engineering Branch.
8506050357 850312 PDR    FOIA                                                  1    "' M ". Cc:ir ORABER85-128                PDR
                                                                                  . rold R. Denton, Director
        *SEE PREVIOUS PAGE FOR CONCURRENCES                                    Ofpce of Nuclear Reactor Regulation                                          f ome > .....9h19..RAB.*..... 9hi .RAB,,*
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                                                            ,,,,,,q((p,RAB *
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em>    .... 8/,1,2,/,82,,,,,, ,,,,,8 g,6 /,82 ,,,,, ,,,,,80 6,[,82,,,,,  ,,,,,8/,1,9/,82,,;, ,,,,,8@ 82, . ,,, ,, ,,,$, 82.,,,,              ,,,      281
  .ac roau sis oo.nomacu eno                                  OFFICIAL RECORD COPY                                                                        usceo m . .
_ - _ _ _ _}}

Revision as of 16:49, 21 August 2022

Discusses Effects of Fire Protection Sys Actuation on safety-related Equipment.Issue May Not Have Been Adequately Considered.Div of Engineering Reviewing Recent Fire Sys Actuations
ML20129B897
Person / Time
Issue date: 08/27/1982
From: Harold Denton
Office of Nuclear Reactor Regulation
To: Michelson C
NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD)
Shared Package
ML20129B878 List:
References
FOIA-85-128 NUDOCS 8506050357
Download: ML20129B897 (1)


Text

- - -

.. < r .'

Central Files DEisenhut ORAB Rdg GHolahan HDenton DPickett ECase SCavanaugh PPAS (NRR-82-306 '

SHanauer DNottingham RMattson (NRR-82-306 '

RVollmer EMORANDUM FOR: Carlyle Michelson, Director HThompson Office for Analysis and Evaluation PCheck of Operational Data BRnvder 6LEergusoD FROM: Harold R. Denton, Director VBenaroya Office of Nuclear Reactor Regulation MChirmal, AE00 SUB_ JECT: EFFECTS OF FIRE PROTECTION SYSTEM ACTUATION ON SAFETY-RELATED EQUIPMENT As discussed in the AEOD memorandum on the above subject dated Janaury 28, 1932, recent operating reactor events show that s'afety-related equipment subjected to water spray from fire protection systems can be rendered l inoperable. The events also indicate that spurious actuation of fire protection systems can be initiated by operator error, steam flow, high humidity or maintenance activities in the vicinity of fire protection system detectors. These events tend to show that the interactions between fire protect. ion systems and other systems that affect.the operation of safety-related systems may not have been adequately considered.

The AE00 memorandum of July 28,1982, " Carbon Dioxide Systems Used for Fire Protection In or Adjacent to Critical Areas," discusses the inadver-

' tent actuation of the CO2 system in the Grand Gulf ECCS penetration room.

The CO2 system overpressurized the penetration room and consequently forced ppen the locked door 'to'the auxiliary building. In addition to the event description, a number of questions relating to carbon dioxide fire protec-tion systems were raised. We consider the Grand Gulf event to be an extension of the original concem.

GDC 3 states, inppart "Firefighting systems shall be designed to assure that their rupture and inadvertent operation does not significantly impair the safety capability of these structures, systems, and components." Branch Technical Position CMEB 9.5-1 to BTP 9.5.1 has additional functional criteria for CO2 systems. During the Operating Reactor Event meeting of January 7, 1982 the Division of Engineering was assigned to review the recent fire system actuations and consider the need for modifications to requirements; or reviews. The DE study is ongoing and will consider the AEOD concern for a11 ' types of fire protection systems (e.g., water, halides, carbon dioxide and other chemicals).

We will inform you of any recommendations that may result from this study.

Additional information may be obtained from the Chemical Engineering Branch.

8506050357 850312 PDR FOIA 1 "' M ". Cc:ir ORABER85-128 PDR

. rold R. Denton, Director

  • SEE PREVIOUS PAGE FOR CONCURRENCES Ofpce of Nuclear Reactor Regulation f ome > .....9h19..RAB.*..... 9hi .RAB,,*

0 ,,,,,

,,,,,,q((p,RAB *

,,,pE,,:,Q,I.,R* , , , , , ,

,,p ,

Q/ ,,A, ,,,pk , , , , , , , ,hk@,

sua 4 > .DP.19.kRtt;s.w. ...GH,o,la ha,n...... ...Hp.R9.).it9.... . ...RYQllmet... ... H 0. . . o... ... . n t .. .Hbenton.....

em> .... 8/,1,2,/,82,,,,,, ,,,,,8 g,6 /,82 ,,,,, ,,,,,80 6,[,82,,,,, ,,,,,8/,1,9/,82,,;, ,,,,,8@ 82, . ,,, ,, ,,,$, 82.,,,, ,,, 281

.ac roau sis oo.nomacu eno OFFICIAL RECORD COPY usceo m . .

_ - _ _ _ _