ML19338F613
| ML19338F613 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/15/1980 |
| From: | Braulke G GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| References | |
| RTR-NUREG-0588, RTR-NUREG-588 ISSUANCES-SP, NUDOCS 8010200687 | |
| Download: ML19338F613 (12) | |
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- a LIC'10/15/80 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION
'BEFORE THE.. ATOMIC SAFETY AND LICENSING BOARD In-the. Matter of
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METROPOLITAN EDISON COMPANY
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Docket No. 50-289
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(Restart)
.(Three Mile Island Nuclear
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Station, Unit No. 1)
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LICENSEE'S TESTIMONY OF
. GEORGE R.
BRAULKE
~~.N RESPONSE TO BOARD-QUESTIONS ON UCS CONTENTION-12 4
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' OUTLINE
-The purposes 1and objectives-of this testimony are to. respond to three Board-questions? relating to UCS Contention 12.
The-testimony shows that the:only environmental stress to which certain. safety-related: equipment at TMI-2 was exposed that was beyond: conditions for which it'was qualified was submergence'
'duerto flooding and that appropriate corrective actions are being taken at TMI-1. ~ The: testimony also explains'whyLRegu-
- latory Guide 1.89 does not apply 1to TMI-1, and why the environ-mental. qualification investigation of safety-related. electrical equipment, ordered byithe Commission, provides reasonable assurance of safe operation at TMI-1.
Finally, the testimony identifies the environmental qualification criteria which equipment inside of -containment must meet with. respect to radiati'onJ1evels;a'nd length of time of exposure.
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16 INTRODUCTION
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This testimony,fby Mr. George R. Braulke,'GPU Senior Electrical Engineer,-is addressed to-the three Board Questions regarding Cc3 Contention No. 12.
Each question is quoted below,. followed imme--
diately by Licensee',s response to.the question.
/
FIRST BOARD' QUESTION REGARDING UCS CONTENTION 12
- The TMI-2 accident demonstrated that some safety-related equipment may have been exposed-or was in imminent danger.
of being exposed to environmental-stresses beyond that for which it was qualified.
The board's concern.is primarily with such equipment qualification. -In addition, environ-mental stresses to safety-related equipment will be of concern to the, extent that such equipment is not included in existing staff requirements.
RESPONSEE BY WITNESS BRAULKE:
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As stated in my separate testimony.on UCS Contention 12
- (Licensee's ' Testimony of Robert W. Keaten, George R.
Braulke and George J.
Brazill in Response to UCS Contention No. 12, UC3 Contention No. 14.and!UCSLContention No. 3 (Safety Classi-ficstio7),Jdated September. 15, 1980), the only environmental.
-stress-to~which certain-safety-related equipment at TMI-2
. was exposed-that was beyond conditions - for which it was r
squalifiedLwas. submergence'due to flooding.
Corrective L
JeffortsLat;TMI-1.will be' completed prior to restart to e
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Epreventfthe 4 stibmergence 'o'f 11mportantlinstruments. - Also,1see' ~
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..the response below<tolthe second' Board Question.
SECOND' BOARD' QUESTION REGARDING UCS-CONTENTION 12 Which? items l:of-Regulatory Guide 1.89 have been grandfathered-
...w th respect toiTMI-1?. Explain any-j ustification-for i
allowing restart without' compliance with the grandfathered j
-items.
I
RESPONSE
y BY WITNESS'BRAULKE:
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The Implementation section of Regulatory. Guide 1.89 states as'follows:
This guide reflects current regulatory' practice.
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Th,erefore,' except in those c~ases in which the-applicant 4
proposes.an. acceptable' alternative method for-complying 1:
with specified portions of:the Commission's---regulations, this-guide---will;be used:by~the Regulatory l staff in evaluating-all.' construction permit applications for U
which the-issue date.of the Safety Evaluation Report' (SER) -is July 1, 1974',- or after.
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'Forythose construction permit applications for which j
an:SER was?is' sued priorito July.l',-1974, the. Regulatory istaffemay,. subsequent to issuance of the' construction permit-(or operatingilicense)',.' reevaluate the Safety Analysis Report:on.a~. case-by-case.' basis to assure-that acceptable' methods for qualification of. Class:IE equip-
-ment have been specified.in. purchase orders executed
. for such equipment Jon or. after November ~ 15, 1974.-
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.TMI-I received:its operating licenseiin. April, 1974.
Consequently, t
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Regu1atory! Guide 11.89Ldoes-not applyr.to TMI-l'.-
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.Nevertheless~,dthe' objective-of'having. safety-related' equip-
- ment designedito' accommodate theLeffects of,fand to be. compatible-
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Twith, associated environmental. conditions,.includingTaccidents,-
wasSfactore'dLintofspecification development and equipment evalua-
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- functionb theLpostulated' accident" conditions, operating;t.2a
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requirements,--and'infsome instances: specific type.testsLto be performed. ~ The.resultsLof the safety-related equipment qualifi-cation ~' investigation 1 initiated by IE Circular 78-08 and IE Bulle-tin 79-01, and performed byLLicensee, has' discovered no evidence-s to'date?upon which to conclu'de that this objective was not realized.
As stated by the Ccemission'in Petition for Emergency and Remedial Action,- CLI-80-21', 11 N.R.C.
707L(1980), the DOR Guide-Llines and.NUREG-0588 provide more definitive criteria than Regu-latory Guide 1.89 for the environmental qualification'of safety-related electrical equipment.
In that-same decision, the Commiss1on ordered the-use of'the DOR Guidelines, which provide a level of-confidence essentially equivalent to tdtat which would j
be achieved :from; the application of IEEE-323-1974, to review j
operating-plants,l'and NUREG-0588 to review plants under licensing review.
The Commission'also ordered that those-documents form
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'the requirements 2which must be~ met in' order to satisfy those:
aspects o:
Teral Design: Criterion'4 of Appendix A to-10 C.F.R.
PartJ50'which relate to environmental qualification of safety-relatedfelectrical equipment.
The Commission ordered that by
'no laterfthan'JuneJ30,11982,- all. safety-related' electrical equipmenttiniall operating plants'sha11Lbe qualified to the
' DOR Guidelinescor NUREG-0588. _The commission further stated 4
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- that current NRC requirements and those actionsJordered in-CLI-80-21
. provide-reasonable-assurance th'at the public health and-safety is adequatelyLprotected during the tima necessary for corrective
' action.
The environmental qualification. investigation of safety-
-related electrical equipment subjected to_possible harsh environ-l ments under IE Bulletin;79-01B will identify any components'that do not conform to cne DOR Guidelines or where adequate documenta-tion 11s'not avai_able to demonstrate conformance.
In such in-
. j stances, corrective action will be taken in accordance with the requirements of IE Bulletin 79-01B.
THIRD BOARD QUESTION REGARDING UCS CONTENTION 12 L
What are the environmental qualification criteria which equipment inside of-containment must meet with respect l
to radiation levels and length of _ time of exposure?
L (Address the Interim Staff' Position on Environmental
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4 Qualification of Electrical' Equipment, NUREG-0588).
RESPONSE
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BY WITNESS BRAULKE:
L As: stated in_my separate testimony in response to UCS Con-tention 12,cthe level.of radiation to which safety-related
-equipment-inside: containment at.TMI-1 must be qualified is the 7
conservativeidose'of12x10 Rads. (gamma), as suggested'in the f
L DOR." Guidelines.for Evaluating Qualification of Class lE
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-Electrical Equipment in10perating Reactors'."
That value iJ
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-based on the methods..andcs' ample-~ calculations:describedLin
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Appendix DfofNUREG-0588..-Factors;can-be applied to the con-
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servative-dose' to : correct' the dose in specific instances.~ for
' shielding ;and ' for' the! time equipmentfis' required to remain functional..These-l factors are-detailed in the DOR Guidelines.
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' GEORGE R.
BRAULKE
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- Business Address:
.GPU Service Corporation 100 Interpace Parkway Parsippany,.New Jersey 07054 Education:
- B.'S.,
Electrical. Engineering, Pennsylvania State University,-1969.
M.B. A.,. Seton Hall : University, 1974
~
(concentration in Quantitative Analysis).
" Qualification of Safety-Related. Equipment for Nuclear-Power ~ Generating Stations,"
Drexel. University /IEEE, 1978.
Applied Protective Relaying Course, Westinghouse Electric Corporation,1969.
Experience:
Senior Electrical Engineer, GPU Service Corporation', 1978 to present.
Cognizan t engineer on environmental qualification of safety-related electrical equipment with responsibility for evaluating vendor plans and documentr. tion pursuant to IEEE-323-1974 criteria.
Participated in preparation ani development of nuclear power plant elec-trical system design criteria, equipment rating calculations and equipment spe-cifications.
Product Engineer, Instrument Division, Westinghouse Electric Corporation, 1973 to 1978.
Participated.in the environmental and seismic qualification program for
' Westinghouse protective; relays for use in nuclear power stations.
Additionally, served as -Instructor for the Westinghouse Applied Protective Course.
Negotiations Engineer, Westinghouse
. Electric Corporation,1969 to 1973.
Provided technical information and product proposals: en protective relays and relay systems.
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Professional'
/ Affiliations:
EPRI/ Utility Equipment 'lQualific'ation
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. Babcock &'Wilcoxlowners': Group Environ-mental'-Qualification Subcommittee.
Combustion Engineering Owners' Group Environmental Qualification Subcommittee.
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' UNITED STATES i.T AMERICA
. NUCLEAR REGULATORY COMMISSION BEFORE'THE ATOMIC SAFETY'AND LICENSING BOARD "In the Matter of
)
)
METROPOLITAN EDISON; COMPANY
).
Docket No. 50-289
.)
(Restart)
(Three' Mile Island Nuclear;
)
' Station, Unit No.-1)
)
CERTIFICATE OF SERVICE I'hereby certify that copies of'" Licensee's Testimony of George-R. Braulke in Response to Soard Questions on UCS Con-tention 12" dated October 15, 1980 were served upon the following by personal delivery at the hearing session in Harrisburg,
.Pennsy:l,vania on October 15,:1980 and on.those identified below with~an asterisk by deposit in the U.S. mail, first class, postage ' prepaid, this 16th day of October, 1980.
L Thomas'A. Baxter
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UNITED-STATES OF AMERICA-NUCLEAR. REGULATORY COMMISSION 3ETOREiTHE" ATOM 5C SAFITY AND'L CENSING 30ARD In the: Matter'of'
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METROPOLITAN EDISON, COMPANY-
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Docket No. 50-289
)
(Restart)
-(Three Mile. Island Nuclear _
)
Station, Unit No. 1)
)
1 SERVICE LIST Ivan W. Srith, Esecire Jchn A. Ierln, Esqcire C = 4 "an
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20555 Karin W. Carte.r, Esquire Cr.'hal er E. Oc:fa.
Assis a.nt At:cIney General At:2-ic Saferf;and Licensi.g
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