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See also: [[followed by::IR 05000397/1987009]]


=Text=
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{{#Wiki_filter:REGULAT INFORMATION
{{#Wiki_filter:REGULAT     INFORMATION DISTRIHUTIO 'STEM (RIDS) o ACCESSION NOR: 8709100371       DOC. DATE: 87/09/01     NOTARIZED: NO         DOCKET FACIL: 50-397   WPPSS Nuclear Progecti   Unit 2i Washington Public     Poee 05000397 AUTH. NAME           AUTHOR AFFILIATION ORENBENi G. C. Washington Public Power Supply System       .
DISTRIHUTIO
RECIP. NAME         RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
'STEM (RIDS)o ACCESSION NOR: 8709100371
 
DOC.DATE: 87/09/01 NOTARIZED:
==SUBJECT:==
NO DOCKET FACIL: 50-397 WPPSS Nuclear Progecti Unit 2i Washington
Discusses supplemental respnse to Insp Rept 50-397/87-09 re plans to make post-trip reviee committees more effective in determining causative factors of events. Implementation of planned changes does not supplant existing procedure.
Public Poee 05000397 AUTH.NAME AUTHOR AFFILIATION
DISTRIBUTION CODE:     IE01D COPIES RECEIVED: LTR         ENCL     SIZE:
ORENBENi G.C.Washington
TITLE: General   (50 Dkt)-Insp Rept/Notice of     Violation   Response NOTES:
Public Power Supply System.RECIP.NAME RECIPIENT AFFILIATION
RECIPIENT         COPIES            REC IP IENT        COPIES ID CODE/NAME       LTTR ENCL       ID CODE/NAME       LTTR ENCL PD5 PD                              SAMWORTHi R INTERNAL: ACRB                   2            AEOD                    1 DEDRO                   1          NRR MORIBSEAUi D NRR/DOEA DIR           1          NRR/DREP/EPB            1 NRR/DREP/RPB           2            NRR/DRIS DIR            1 NRR/PMAS/ ILRB         1          0    I ERMANz J        1 OGC/HDB2               1                                    1 RES DEP Y G 1           1           RGN5     FILE 01       1 TERNAL: LPDR                                NRC PDR NSI C TOTAL NUMBER OF COPIES REQUIRED: LTTR         22   ENCL
Document Control Branch (Document Control Desk)SUBJECT: Discusses supplemental
 
respnse to Insp Rept 50-397/87-09
Washington Public Power Supply System 30008eorge Washington Way P.O. Box968 Richland, Washington 99352-0968 (509)372-5000 September 1, 1987 G02-87-238 Docket No. 50-397 Nuclear Regulatory Commission Attn:   Document Control Desk Washington, D.C. 20555 Gentlemen:
re plans to make post-trip reviee committees
 
more effective in determining
==Subject:==
causative factors of events.Implementation
NUCLEAR PLANT NO. 2 LICENSE NO. NPF-21 NRC INSPECTION REPORT   87-09
of planned changes does not supplant existing procedure.
 
DISTRIBUTION
==Reference:==
CODE: IE01D COPIES RECEIVED: LTR ENCL SIZE: TITLE: General (50 Dkt)-Insp Rept/Notice
Letter, G02-87-218,   G. C. Sorensen   (SS) to J. B. Nartin (NRC-RV), same subject, dated July 17,     1987 In the referenced letter the Supply System committed to provide this supplemental response to NRC Inspection Report 50-397/87-09 regarding our plans to make post-trip review committees more effective in the determination of causative factors pertaining to events.
of Violation Response NOTES: RECIPIENT ID CODE/NAME PD5 PD COPIES LTTR ENCL REC IP IENT ID CODE/NAME SAMWORTHi R COPIES LTTR ENCL INTERNAL: ACRB DEDRO NRR/DOEA DIR NRR/DREP/RPB
A detailed evaluation of Plant Procedure 1.3.5, "Reactor Trip and Recovery", has been performed and, as a result, the procedure will be revised to include the following improvements:
NRR/PMAS/ILRB OGC/HDB2 RES DEP Y G 1 TERNAL: LPDR NSI C 2 1 1 2 1 1 1 AEOD NRR MORIBSEAUi
: 1. The followup review committee   will be assembled immediately following any reactor   trip unless otherwise directed by the Plant Nanager.
D NRR/DREP/EPB
: 2. When personnel performance   is   a contributing factor to an event, a peer review committee       will be formed to evaluate the decision processes.
NRR/DRIS DIR 0 I ERMANz J RGN5 FILE 01 NRC PDR 1 1 1 1 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL  
: 3. Predetermined   experts will be relied upon for cause investigation in support of the restart decision process.
Washington
It should be noted that this aspect is currently effectively.
Public Power Supply System 30008eorge
performed and the change is to document who the resources are and facilitate management of the group.
Washington
I             j09 87Q910037f 8osooos pDR ADocK j
Way P.O.Box968 Richland, Washington
9
99352-0968
 
(509)372-5000
Nuclear Regulatory Commission Page Two September 1, 1987 NRC INSPECTION REPORT     87-09
September 1, 1987 G02-87-238
: 4. If   the   cause(s)   of a   reactor   trip are indeterminate, a surveillance method will be developed,               if   possible, to monitor the component/system response following restart.
Docket No.50-397 Nuclear Regulatory
: 5. Independent       verification will be required of significant conclusions relied upon in the restart decision process and root   cause assessment.
Commission
It is anticipated that the procedure will be revised by November 30, 1987; however, in the interim, a management letter has been issued which directs personnel to follow the intent of the changes.                     It should be noted that implementation           of these planned changes does not supplant the existing procedure.             Until such time that the procedure is revised, these changes are         to   be considered as enhanced process policy, with Plant Management           as   the primary implementor of this policy.
Attn: Document Control Desk Washington, D.C.20555 Gentlemen:
Should you have any questions         regarding our response,       please do not hesitate to contact     me.
Subject: NUCLEAR PLANT NO.2 LICENSE NO.NPF-21 NRC INSPECTION
Very truly yours, G. C. Sor nsen, Manager Regulatory Programs JDA/tmh cc:   J. B. Martin   - NRC RV R. B. Samworth     - NRC C. J. Bosted 901A
REPORT 87-09 Reference:
 
Letter, G02-87-218, G.C.Sorensen (SS)to J.B.Nartin (NRC-RV), same subject, dated July 17, 1987 In the referenced
e I}}
letter the Supply System committed to provide this supplemental
response to NRC Inspection
Report 50-397/87-09
regarding our plans to make post-trip review committees
more effective in the determination
of causative factors pertaining
to events.A detailed evaluation
of Plant Procedure 1.3.5,"Reactor Trip and Recovery", has been performed and, as a result, the procedure will be revised to include the following improvements:
1.The followup review committee will be assembled immediately
following any reactor trip unless otherwise directed by the Plant Nanager.2.When personnel performance
is a contributing
factor to an event, a peer review committee will be formed to evaluate the decision processes.
3.Predetermined
experts will be relied upon for cause investigation
in support of the restart decision process.It should be noted that this aspect is currently effectively.
performed and the change is to document who the resources are and facilitate
management
of the group.I 87Q910037f
8 j09 pDR-ADocK osooos j 9  
Nuclear Regulatory
Commission
Page Two September 1, 1987 NRC INSPECTION
REPORT 87-09 4.If the cause(s)of a reactor trip are indeterminate, a surveillance
method will be developed, if possible, to monitor the component/system
response following restart.5.Independent
verification
will be required of significant
conclusions
relied upon in the restart decision process and root cause assessment.
It is anticipated
that the procedure will be revised by November 30, 1987;however, in the interim, a management
letter has been issued which directs personnel to follow the intent of the changes.It should be noted that implementation
of these planned changes does not supplant the existing procedure.
Until such time that the procedure is revised, these changes are to be considered
as enhanced process policy, with Plant Management
as the primary implementor
of this policy.Should you have any questions regarding our response, please do not hesitate to contact me.Very truly yours, G.C.Sor nsen, Manager Regulatory
Programs JDA/tmh cc: J.B.Martin-NRC RV R.B.Samworth-NRC C.J.Bosted-901A  
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}}

Latest revision as of 08:19, 4 February 2020

Submits Supplemental Response to Insp Rept 50-397/87-09 Re Plans to Make post-trip Review Committees More Effective in Determining Causative Factors of Events.Implementation of Planned Changes Does Not Supplant Existing Procedure
ML17279A552
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 09/01/1987
From: Sorensen G
WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
GO2-87-238, NUDOCS 8709100371
Download: ML17279A552 (4)


Text

REGULAT INFORMATION DISTRIHUTIO 'STEM (RIDS) o ACCESSION NOR: 8709100371 DOC. DATE: 87/09/01 NOTARIZED: NO DOCKET FACIL: 50-397 WPPSS Nuclear Progecti Unit 2i Washington Public Poee 05000397 AUTH. NAME AUTHOR AFFILIATION ORENBENi G. C. Washington Public Power Supply System .

RECIP. NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Discusses supplemental respnse to Insp Rept 50-397/87-09 re plans to make post-trip reviee committees more effective in determining causative factors of events. Implementation of planned changes does not supplant existing procedure.

DISTRIBUTION CODE: IE01D COPIES RECEIVED: LTR ENCL SIZE:

TITLE: General (50 Dkt)-Insp Rept/Notice of Violation Response NOTES:

RECIPIENT COPIES REC IP IENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 PD SAMWORTHi R INTERNAL: ACRB 2 AEOD 1 DEDRO 1 NRR MORIBSEAUi D NRR/DOEA DIR 1 NRR/DREP/EPB 1 NRR/DREP/RPB 2 NRR/DRIS DIR 1 NRR/PMAS/ ILRB 1 0 I ERMANz J 1 OGC/HDB2 1 1 RES DEP Y G 1 1 RGN5 FILE 01 1 TERNAL: LPDR NRC PDR NSI C TOTAL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL

Washington Public Power Supply System 30008eorge Washington Way P.O. Box968 Richland, Washington 99352-0968 (509)372-5000 September 1, 1987 G02-87-238 Docket No. 50-397 Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen:

Subject:

NUCLEAR PLANT NO. 2 LICENSE NO. NPF-21 NRC INSPECTION REPORT 87-09

Reference:

Letter, G02-87-218, G. C. Sorensen (SS) to J. B. Nartin (NRC-RV), same subject, dated July 17, 1987 In the referenced letter the Supply System committed to provide this supplemental response to NRC Inspection Report 50-397/87-09 regarding our plans to make post-trip review committees more effective in the determination of causative factors pertaining to events.

A detailed evaluation of Plant Procedure 1.3.5, "Reactor Trip and Recovery", has been performed and, as a result, the procedure will be revised to include the following improvements:

1. The followup review committee will be assembled immediately following any reactor trip unless otherwise directed by the Plant Nanager.
2. When personnel performance is a contributing factor to an event, a peer review committee will be formed to evaluate the decision processes.
3. Predetermined experts will be relied upon for cause investigation in support of the restart decision process.

It should be noted that this aspect is currently effectively.

performed and the change is to document who the resources are and facilitate management of the group.

I j09 87Q910037f 8osooos pDR ADocK j

9

Nuclear Regulatory Commission Page Two September 1, 1987 NRC INSPECTION REPORT 87-09

4. If the cause(s) of a reactor trip are indeterminate, a surveillance method will be developed, if possible, to monitor the component/system response following restart.
5. Independent verification will be required of significant conclusions relied upon in the restart decision process and root cause assessment.

It is anticipated that the procedure will be revised by November 30, 1987; however, in the interim, a management letter has been issued which directs personnel to follow the intent of the changes. It should be noted that implementation of these planned changes does not supplant the existing procedure. Until such time that the procedure is revised, these changes are to be considered as enhanced process policy, with Plant Management as the primary implementor of this policy.

Should you have any questions regarding our response, please do not hesitate to contact me.

Very truly yours, G. C. Sor nsen, Manager Regulatory Programs JDA/tmh cc: J. B. Martin - NRC RV R. B. Samworth - NRC C. J. Bosted 901A

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