ML20004E377
| ML20004E377 | |
| Person / Time | |
|---|---|
| Issue date: | 07/02/1979 |
| From: | Butcher E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19252A551 | List: |
| References | |
| FOIA-81-97, RTR-NUREG-0588, RTR-NUREG-588 IEB-79-01, IEB-79-1, NUDOCS 8106120112 | |
| Download: ML20004E377 (13) | |
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PURPOSE OF BULLETIN 79-01 l
l Identify Electrical Equipment Required to Function Under Accic.ent Concitions and Determine Adequacy of Environmental Qualification j
m..
i BULLETIN OBJECTIVES 1
- Expedite Licensee Review of Electrical Equipment Qualification
?
i
- Require Prompt Evaluation and Report of Unqualified Equipment p
- Require Documentation of Qualification of l
Equipment
- Component Description f
- Accident Environment i
- Qualification Environment s.
l
- Manner of Qualification l
l
- Feedback Generic Issues to All Facilities L
I RESPONSIBILITY FOR ACTIONS IE NRR 4
1 Screen 120 Day y
Reports Review 24 Hr 1
Reports i
U Act on Deficient Reports y
gr
. Conduct Interim Prepare Guidelines
' Review (NUREG) for Final Review y
}
Enforcement Action l
i l
3 r 1 r Conduct Final l
Review l
+
Resolve Opeh"'
j issues l'
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INTERIM REVIEW 1
- Per"ormed by Task Group l
Regional Personnel l
IE:HQS NRR
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- FSAR Commitments for Qualification
- Verification of Reports by inspections i
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1 i
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IE BULLETIN 79-01 24 HR. REPORTS OF UNQUALIFIED CLASS IE EQUIPMENT i
s l
Component No. of Plants Reporting NAMCO Valve Stem Mounted 14 Plants at 9 Different Stations Limit Switches i
i Containment isolation Valve Operators 3 Plants at 1 Station insulated instrument and Control Cable 2 Plants at 1 Station Terminal Lt'gs Aluminum Limit Switch Housings on 2 Plants at 1 Three Unit Station Containment isolation Valves h
ASCO Pilot Solenoid Valves for Misc.
10 Plants at 7 Different Statior.s Valve Air Operators l
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SUMMARY
AND STATUS OF i
l CORRECTIVE ACTIONS j
1 3T Plants Have Reported Unqualified Equipment
- All Have Agreed to Replace Equipment Where a Safety Function is Affected
- Six Plants Have Completed Replacement; All Will Be Completed by Next Refueling l
Continued Operation Pending Replacement is Based on a Plant Specific Evaluation of a Combination of the Following Factors 1
)
- Redundant / Diverse Component j
- Importance of the Function (e.g., Indication Only) f
- Locking Component in the Safety Position 4
{
- Administrative Action and Operating Procedures 1
- Recent Operability Tests and inspections
- Post Accident Mitigating Actions Available i
- Fail Safe Design Features i
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GUIDELINES AND ACCEPTANCE CRITERIA FOR FINAL REVIEWS l
l Will Be Developed by DOR in Conjunction With a l
Preliminary Review of Selected Licensee 120 Day Responses and SEP Information l
General Acceptance Guidelines Will Be j
Established With Particular Emphasis on the l
Following Aspects of IEEE 323-1974 l
Service Conditions Radiation Test Sequence Aging Margin Testing and Analysis Methods 4
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EQUIPMENT QUALIFICATION AGONG l
~
)
REG GUIDE 1.89 F3EQUIRES:
- IEEE STD 323-1974 Including Aging for SER's issued After July 1,1974 l
l
- Aging Not Required for SER's issued Before July 1,1974 i
l Ongoing Aging Programs:
I
- NRC Confirmatory Research Program Studies Discussed in NUREG-0413
-Single Environment - Combined Environment
- Rate Effects
- Alternate Damage Indicators
- SEP Aging Reviews Discussed in NUREG-0458 l
-Operating Experience l
- Maintenance and Surveillance Records
-Specific Consideration of Cable Aging j
including On-Site inspections l
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PENDING COMPLETION OF i
l PORTIONS OF THE SEP AND THE CONFIRMATORY RESEARCH PROGRAM DEALING WITH AGING, THE STAFF HAS NOT REQUIRED THAT AGING BE ADDRESSED IN j
THE LICENSEE'S RESPONSES TO l
IE BULLETIN 79-01 J
r.
l
i IE BULLETIN 79-01 TASK l
ORGANIZATION 1
)
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Screen 120 Day Continue j
Reports Review of 4
24 Hr. Reports Enforcement of Unqualified l
Action Equipment v
v l
Request Additional Pr'epare Guidelines and Info. to Complete Acceptance Criteria l
Reports as for Final Reviews Required I
4+
l Final Review Against l
Acceptance Criteria Transfer Exceptions to DOR I
4 r.
Resolve Open issues and Document Staff j
Positions l
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l STATUS OF QUALIFICATION j
DOCUMENTATION l
- Eleven Under SEP Review l
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- Four Received Extension 1
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- Twenty-Seven Preliminary Screening
- Thirty-One Total Responses Received to Date
- Fifty-Eight Total Responses Required i
l PRELIMINARY SCREENING RESULTS Proportion of Components Qualified by Test Proportion of Components Qualified by Analysis Proportion With Questions Remaining i
1 Q.UALIFICATION OF CLASS 1 E SAFETY RELATED EQUIPMENT /A-241 t
KEY PERSONNEL iASK STATUS TASK MANAGER
^.SzumiEwicz x2sd27
,ggg gggg The NRC traff has worked with the nuclear industry to develop The ese standards fee equipment qualification and documentation wouch
,,,,,,n will assure the high level of equipment reliebahty required for nuclear applications. This offort has culminated in the develop.
mont of IEEE Stendard 323. *'IEEE Standard for oualifyine
,g is.,
Class 1E Equipment for Nuclear Power Generating Stations
l This standard and its ancillary standards have provided the focal point for the development of environmental quelsface-Se erel "Sc""^"z x2ms tmn mqui,.n.a in mont v.,s.
,,ni.
OMPA ANALYST IEEE Stendard 323 was first issued as a trait use stendeed
- '*9" (IEEE Std. 3231971) in 1971 and later. efter substential Ceae* H revisior', as a final standard (IEE E Std. 3231974) in 1974.
Both versions of the standard set forth basic requirements for environment,1 qualifiention of electrical equipenent.
)
Specific qualification methods and procedures have been
,p ypg gggggggq reviewed and approved by the NRC staff on a esse-by.
a nJus ask u a 653 kng, case basis es e part of individual heensing actions. These licensing actions include initial construction permit one O
NAME BRANCH
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- TECHNICAL ASSISTANCE CONYACT STATUS
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SLIPPAGE ANALYSIS T. ouuuluo
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MM M MM i Rurs cssiosi g'
- a. wERuiEi.
assios' 1978 ANNUAL m
REPORT i.2.
- ACRS INTERFACE INFORMATION f
Environ.nental qualification hos been discussed with the ACR$
duri,i, s,ecific iant revi.ws during the d.veiupment e<
4
" " '.es uuREG.osa8 (for commenii has been provided io p
CURRENT
- usy s. issi the ACRS. A meeting may be held with the ACRS prior to issuing NUR EG4588 in final form,(which will include staff a
resolution of the public comments,.
- STANDARDS INTERFACE INFORMATION u
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NT 1
iAGER f
,,~oicmS cn m.,. mo.uulo.
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FESRUA W 13.1988 AS OF WEEK ENDING:
wienery nature of the process of developeng nont;lqualification requ6rements and the case-by.
dementition tf them het resulted in a diversity ade 6n ces and dif forent levels of documeneteen stent le which equipment le quelsfied.
sepects of egy6pment qualeficetion are beang pursued at a ty the NRC staf f and the nuclear mdustry on a ses.s. en erder to echeeve e more uniform emplementetson rements established in IEE E Stenderd 323 1974 Ted A-24 es one of these actevities. It mvolved the ment El interem NRC staff positions regarding how the nents af IEEE Standard 3231974 can be met.The petoons f orm th s basis f or licensing reviews of cat qu11ef scetion programs.
A, g
DES It!TERFACE INFORMATION None i
POTENTIAL PROBLEMS Yesti mcneger 6s deteeled to FOB for 3 months resultmg 6n (eltv km completion of final report. Review of revesed t AunE3 by EOS has beest delayed by higher preersty wor k.
STATUS
SUMMARY
NU AE04588 contenning the Interte position was leeued les somment en January 1980. Followmg a 60 day public pomment pereed the staff as 6mplementing these positione in lhe reviews af the equipment qualefecation programs for the Meer Term Operatens License opphcetions. and in the Leeensing reveews for new plants.
The public tomment period terminated on March 17,1980, however; comments were stall being receeved. and accepted sente May 1980 All public comenents and most staff coenstants have been e.icorporated in a dratt of ple fmal NU".E C. A delay in completeen of the final PfD REG es resguered 43 provide time for properation and resolution of I EOs somments, I
QUALIFICATION OF CLASS 1E
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SAFETY RELATED EQUIPMENT (A-24) a
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