ML20245D397
| ML20245D397 | |
| Person / Time | |
|---|---|
| Site: | LaSalle, 05000000 |
| Issue date: | 05/13/1988 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Bliss H COMMONWEALTH EDISON CO. |
| Shared Package | |
| ML20245D268 | List: |
| References | |
| GL-88-07, GL-88-7, NUDOCS 8805230093 | |
| Download: ML20245D397 (3) | |
Text
.
4 Reference-.2.3 i
W May 13, 198S-Ncket No. 50-374-Mr. Henry E. Bliss i
Nuclear Licensing Manager
- Comonwealtn Edison Company Post Office' Box 767 Chicago, Illinois 60690
Dear Mr. Bliss:
ENVIRONMENTAL QUALIFICATION OF OUNKER RAMO
SUBJECT:
CONTAINMENT PENETRATIONS AT LASALLE STATION, UNIT 2 During a Recion III Environment! Qualification (EQ) Inspection at the Braidwood Station conducted during February and March 1988. it was determined that the l
environmental qualification of four Bunker Ramo containment penetration assemblies !
In response to a recent request, you had not been coequately demonstrated.
provideo information regarding the verification of qualification for Bunker Thedocumentation(test Ramo penetration assemblies installed at LaSalle 2.
reports) used to support your position that these penetration assemblies are qualified is.the seme or similar to that used for Braidwoo to concluce enat operability un::er design basis events has been fully After reviewing tais information, we conclude that environment'al qualification has still not been demonstrated for these-demonstrated.
assemblies.
Since E0 has not yet been e,taclisnec far the Bunker Remo penetrations installe 88-07,
- at LaSalle 2, you should follow the guidance identified in Generic Letter "Enytronmental Qualification of Electrical Equipment Im q
Continued Operation, However, your evaluation in support I
This letter does not require any response.of making a finding'of ope regarding the demonstration of equipment operability.
Oliginal pgned by K
Dennis M. Crutchfield, Director l
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) e,7 Division of Reactor Projects. Igt,
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IV, Y and Special Projects Office of Nuclear Reector Regulation j
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See next page 4
DISTRIBUTION PD32 Reading Docket Hlc L, Norrholm L. Luther P. Shemanski
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l Ref erence-2,4 Minimum IR Recorded During LOCA (Bunker - Ramo Report 123-2103, Rev. 04)
L.V. EPA Minimum IR Value (12 IPS) in ohms During Date Modules LOCA Application 2-23-78 3 X TRIAX 7,000 Conductor to shield Neutron monitoring 22,000 Shield to ground (Non-EQ) 5 2-23-78 3 x 350 3 x 10 Not used at LaSalle 2-23-78 12 # 6 65,000 Conductor to ground Hot used at LaSalle 2-23-78 26 # 20 7,000 Conductor to ground Neutron monitoring (Non-EQ) 2-23-18 60 # 14 2,100 Conductor to ground LV Control (EQ) 2-23-78 98 # 20 7,500 Conductor to ground (Control rod position and indication) (Non-EQ) 2-23-78 102 # 20 15,000 Conductor to ground LV shielded Instrumentation (EQ)
ANC0 letter dated March 11,1988)
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Ref erence-2.6 l'
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- fpr, UNITED STATES 1_
NUCLEAR REGULATORY COMMISSION 7
0FFICE OF NULLEAR REACTOR REGULATION L
WASHINGTON, DC 20555 1:6 w:
May 24, 1988 b_
NRC INFORMATION NOTICE NO. 88-29:DEFICIENCIES IN PRIMARY CONTAINMENT LOW-VOLTAGE ELECTRICAL PENETRATION ASSEMBLIES es$
^5 Addressee _s:
All holders of operating licenses or construction permits for nuclear power t":
reactors.
b" Purcose:
problems resulting from the findings of a recent NRC environmental qualifica-f[
This information notice is being provided to alert addressees to potential It is tion (EQ) inspection concerning low-voltage penetration assemblies.
i expected that recipients will review the information for applicability to their How-p facilities and consider actions, as appropriate, to avoid similar problems.
J ever, suggestions conteined in this infortisation notice do not constitute..HRC_
requirements; therefore, no specific action or written response.is~ required.
~
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Description of Circumstances:
s During an E0 inspection conducted by Region III from February 20, h
Braidwood 2.
1988 to March 4,1988, a deficiency was discovered in test documentation for
[f Insulation resistance readings had not been taken four penetration assemblies.
frequently enough to determine the performance of the assemblies in testing to 9
The first reading simulate conditions for a loss-of-coolant accident (LOCA).
These assemblies were manu-L was taken between 8 and 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> into the test.
[
factured by the Bunker Ramo Company.
i i
In response to the finding, the licensee, Coninonwealth Edison Company, provided a test report (Reference 1) from another plant to demonstrate that the configu-A review of this ration installed at Braidwood 2 is environmentally qualified.
'l test report, however, showed that the insulation resistance readings were not i (
taken at a frequency consistent with the guidance provided in the Institute for 373-1974.
Electronic and Electrical Engineers (IEEE) Standard l
Discussion:
These electrical penetrations are designed to carry some 75 electrical signals from instrumentation inside the containment to main control room indic i
I ff.
a l
IN 88-29 May 24, 1988 Page 2 of 3 protective circuitry while maintaining the integrity of the containment pres-sure boundary.
The deficiency described above relates to the cuality of the signal transmission of the assemblies, not to their pressure-retaining capabilities.
The specific instruments involved provide inputs to the reactor protection system and the engineered safety features actuation system as well as providing certain post-accident monitoring functions.
Some of those functions are re-quired to mitigate a LOCA, a main feedwater line break, and a main steam line break. These are the design basis accidents that produce the harsh environ-ments the penetration must withstand.
During accident conditions, failure of these assemblies could affect the accuracy of Class IE instruments and thus mislead operators.
Instrumentation required +o mitigate the consequences of design basis accidents typically operates on 4 to 20 milliamps; therefore, cable insulation resistance is essential for the accuracy of these instruments.
The qualification informa-tion provided by the licensee did not have cable insulation resistance readings taken frecuently enough to determine the performance of the penetration assem-blies under LOCA simulation testino. Thus, environmental qualification for these assemblies has not been demonstrated (Reference 21 A generic communication addressing similar equipment has been issued 'previously (Reference 31 No specific action or written response is required by this information notice.
If you have any cuestions about this matter, please contact one of the techni-cal contacts listed below or the Regional Administrator of the appropriate regional office, ha 1
. Rossi,s.
tor D
Division of Operat. 1 Events Assessment Of fice of Nuclear Reactor Regulation Technical Contacts:
Ra.i Anand, NRP (301) 492-0805 Vern Hodge, NRR (3011 492-1169 List o* Recently issued NPC Information Notices
Attachment:
Re f erence-2. 7 t
ENVIRONMENTAL QUALIFICATION OF l
BUNKER RAMO INSTRUMENTATION PENETRATIONS LaSalle Licensina Requirements - NUREG 0588 Category II and l
I IEEE 322-1971 I
LaSalle Qualification - NUREG 0588 Category II, IEEE-1971 and performance requirements of IEEE 323-1974.
Qualification Reference - EQ Binder No. EQ-LS062 and IR calculations for Instrumentation applications.
(2 l
Penetrations) i Penetration Tao No.
Application Function 2LV94E Drywell Temp. Monitoring No Trip Function 2LV95E Suppression Pool Temp.
Only Indication Monitoring Qualification Results -
Tested configuration simulates installed configuration at o
LaSalle. (Raychem Splices used in both cases on the inboard side.)
Lasalle Unique Test with high gR values measured o
(19 readings) (Lowest 1.5 x 10 )
IR calculations for the LaSalle application show o
negligible effects for intended function Qualified to NUREG 0588 Category II - Qualified Life 12.8 o
years (Q-Seal limiting)
NRC Concerns vs. Imsalle Resoonse TaSalle Resoonse NRC Concern Low IR values during and LaSalle test shows high IR j
after LOCA Effect of low IR values on No trip function instrument accuracy Only indication LaSalle IR Calculation shows negligible effect Are circuits energized during Circuits energized during DBE/ Post-DBE?
If so, DBE/ Post-DBE justify IR values LaSalle IR calculation shows negligible effect CONCLUSION LaSc 1 penetrations are qualified to NUREG 0588 Categcry II I
requirements
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CON F_E_RE_N_C_E.. CAL L- ~ ~ ~
"00-041659 Date 12-1-88 Time 9.00am Person, Cal i.ef:
Compgnj i
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2.. P. E n; J.
L.,
C;an CECO - Nuc!ed Licensing S. Huns 3aer
- h. L. 'assic CECO - B'..R Eng.
56L - C0D A. Gener)
S&L - CQD J. Sinrappan Person __Ceilin9 Company NRR Staff at Washiraton DC J. Craig P. Sumanski NRR Staff at Washington DC NRR Staff at Washington DC H. Walker Project No.
Project 8406-18 LaSalle County - Unit 2 Subject Discussed Environmental Qualification of Bunker. Ramo /Amphenol Instrumentation Penetrations Installed at LaSalle County Unit 2.
Summary of Di_scussion,. Decisions, and Cor.vnitments The conference call started with an introduction of everyone present.
- 5. Hunsader started the discussion by stating the purpose of the call.
He said that CCCo submitted documentation to NRC through Region III showing qualification of the subject penetration for the specific applications at LaSalle County Unit 2.
This call was to walk them through these documents concluded that these penetrations are qualified and dnd show why CECO has answer any questions NRC staff may have on these document;.
As a first step a comparison of dccument NRC staff received from Region III was made with the document CECO has on the subject to assure that the staff has all the documents they need to complete this review. The comparison indicated that the staff did have all the documents they need.
Then 5. Hunsader requested H. L. Massin to outline the LaSalle County Unit 2 H. L. Massin started his discust on l
i penetrations and their applications.
by stating that he is responsible at CECO for all the engineering efforts on CECO has contracted Sargent & Lundy (S&L) to help LaSalle County Station them in the engineering evaluation of the environmental qualification (EQ) of the subject penetrations and the staff i; discussing the matter with the right personnel.
He stated that the Bunker Ramo penetrations are limited to Unit 2 at LaSalle.
Then he proceeded to explain the number of penetrations l
used at LaSalle and their applications.
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ilectorandun of Telephone Conversation Decenber 1, 1933 EQ of Bunker Rato/Anpnenol Instrumentation Project No. S'.0f-18 Penetrations Installed at LaSalle County COD- 041659
-Unit 2 Dage 2 Tne fol!o..in; < m ire-v-
sn,-
r 22 e
Tot 3' nw,c m of Electri;;i ?ene te"tions in voit 2 6unker Rano/ Ac;phenoi Penetra tions 16 e
e Used in Pressure Integrity applications only 10 4
Used in Class lE Control Circuits e
2 Used in Class 1E Instrumentation Circuits e
At this point NRP staff asked how many of the above penetrations are included in LaSalle Q-list.
H. L. Massin responded saying that all 22 of them are included in the LaSalle 0-List.
He continued saying:
The two instrumentation penetrations feed to instruments that do not have e
any trip function.
They provide only indication.
They are qualified for 12.8 years from August 28, 1985.
e They will be upgraded to NUREG 0588, Cat. I requirements by 1998.
e LaSalle SER requires that all Class 1E equipment in barsh areas be environmentally qualified to NUREG 0588, Cat II requirements e
At that point NRC staff asi !d what is CECO's interpretation of NUREG 0588, Cat Il qualification.
J. Sinnapp1n reported that the only difference between Cat. II and Cat. I qualification is that the aging ef fects can be addressed t.irough material degradation analysis.
NRR staff concurred As for as LOCA is concerned the requirements would be the same.
with this position.
i1r. H. L. Massin continued his discussion saying:
The two instrumentation penetrations feed a total of 18 instruments, e
Four weed thermocouple - They measure drywell ambient temperatures. They o
are Reg. Guide 1.97., Type D, Cat. II Instruments.
Fourteen weed RTD's - They measure local suppression pool water temperature.
e Tney are Reg. Guide 1.97 Type A, Cat i Instruments.
I 1
1 4
Menorandum of Telephone Conversation Decer.ner 1, 1933 o'
E.Q of Bunker Ramo /Amphenol Instrumentation Project u. Mu6-13 Penetrations Installed at LaSalle County CQD-041659 Unit 2 Page 3 e
~% t w r~.oc ca:ia ca cct >:ve anj autc ::ic 'ric Twj only provice 3 l e: r-to 'onteci ca Ers nnel.
No coeretor action is re:;u i red.
e in, kTD's do not nave any autor,atic trip.
They or'y provide alarm to Control Roo:: perscnnel.
Tne operator initiates RHR suppression pool cooling based on these alarms.
Tne penetrations were qualified to Nureg 0588, Cat II requirements.
The e
IR evaluations were done using the data taken during LOCA test.
The evaluations show negligible effect on the circuit accuracy for LaSalle applications.
(
At this point, Mr. H. L. Massin asked J. Sinnappan to provide the details about the qualification program.
J. Sinnappan's discussion is sumnarized below-1 i
The tested and installed configurations are the same because, j
e f
same cables (LaSalle cables used in test) same non-metallic components / materials used only difference being the splice used in test is non-nuclear.
LaSalle installation is Raychem nuclear grade splices inside containment.
This difference is conservative, Functional tests were done.
e Radiation Aging - by test / analysis e
Thermal Aging - by material analysis e
LOCA Test - envelops LaSalle requirements.
e The specimens were exposed tu the following:
F Duration, Hours Te9per_a tu re,
8 342 7
280 5.5 273 15 257 624 244.4 profile envelops the required LOCA profile through TheLDC' test dearadat ion eQJiV3}ency Calculation;.
l 1
l
t f4 Menoran$u of Telephone Conversation December 1, 1988 EQ of Bunker Ramo /A phenol Instruments *. ion Project No. M 06-18 Penetrations Installed at LaSalle County CQD-041659 Page 4 Unit 2
- .,;rned
- 43
- n; ; :1 :,r s.ere ased f2r
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,vrps drd 12]
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.2 Lest
.lodules were CDntinuousl:. enersi:ec witn rated continuous current.
Insulation resistance was measured and recorded periodically throughout the duration of the test.
1 Effects of IR Values e
The minimum IR value measured for instrumentation module, i.e.,
i U
1.33E6 ohr.s, uill resul t in recorded temperatures being 0.2 F 1ess than the actual temperature.
This 0.2 F inaccuracy will not be visibly detectable.
It was datermined that RTD instrument loops are more sensitive to leakage currents than the thernocouples instrument loops.
e Conclusion Based on the above points, we conclude that the Bunker Ramo Penetrations are qualified to Nureg 0588, Cat. 11 requirements for use in LaSalle.
The concerns raised by the NRC staf f during the Braidwood EQ inspection are not applicable.
At this point, NRR pointed out a difference in installed and test configuration in the way they were wired for IR measurement. They also wanted an explanation 3
123-2183.
of low 1R of 2 x 10 ' reported in the Bunker Ramo Test Report Mr. A. K. Behera summarized these as follows:
The instrument test module has 102 conductors (34 twisted pair shielded) and all the conductor connected in series to measure the total leakage e
This is conservative as only one twisted paid shielded conductor resistance.
is used for one instrument loop.
The low IR of 2 x 10'~ (2100: to be exact) is associated with the control Bunker Ramo tested sample had all the modules installed at LaSalle e
(i.e. power, control, instruments tion, triax).
During the LOCA test, IR f
module.
readings were taken for all the modules. Bunker Ramo stated the lowest
/'
123-2183. Although IR measurement on any of the tested smaples in test report the details regarding the IR measurement is not stated in the test report the letters from ANCo Engineers, dated March 11, 1988 and April 18, 123-2183, The lowest IR reported for the 1988 (tab G of EQ-LS062) clarify the issue.(all 102 condutors connected in series) and instrument module is 1.5 x 10' there were at least 19 measurements recorded during the LOCA test.
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December 1,~1988
~
MeborandukofTelephoneConversation.
. Project No. 8406-18 EQ of' Bunker Ramo / Amphenol Instrumentation
, penetrations Installed at LaSalle County-CQD-041659 i
~
Page.5 L Uni t 2:-
NRR Staff l indicated the following:
Results from different tests on these Bunker Ramo Penetrations show il e
inconsistent results.
A.' K. Behera respcnded with the following:
LaSalle has a unique test on samples which are identical'to the installed.
l c
L modules.
.LaSalle application is limited to thermocouple and Resistance Temperature e
Detectors (RTD's).
.The four thermocuples as stated earlier by Mr.. H. L. Massin are only used to
.Thisprovidean.alarmtotheopgrator e-monitog drywell ambient temperature.The normal ambient temperature in the dryw at 140.F.0104 F.-
-Once the accident takes place, the drywell temperature reaches-belgw within a few seconds. These thermocouple will respond to this high.
temperature as the 'IR does not degrade instantaneously into the LUCA, whereas 340 F
~
the LOCA temperature will reach the peak 340 F almost instantaneously.. Also.
0 these thermocouple. feed recorders which nas a maximum range of. 250 F.
- Hence, these recorders w 11 not respond.to the drywell temperature once the thermo-To conclude, the impact of IR on the thermocouple-
. couples sense 250 F.
performance is negligible and. hence, can be eliminated from the evaluation.
i h
.The 14 RTD's as stated earlier by Mr. H.
L.- Massin are used to mon tor t eThenormal e'
suppression pool gater temperature.
These pool is below 100 F and the suppression pool is designed for 20g F.
The RTD's provide an high alarm at 100 F and high high alarm at 110 F.
operator initiates the RHR suppression' pool coo ing mode manually once the The error in the sensed temperature of the suppression pool exceeds 100 F.
5 temperature by the RTD's gsing the lowest measured IR of 1.5' x.10 0 H (1.5 x 10 x 102a) is 0.2 F.
3 action as soon as the suppression pool water reaches 100 F as the error-associated ~.ith it is not detectable to human eye and is also negligible.
The NRC'staf f questioned the usage of 1.5 x 10'O for the Bunker Ramo instrxc t 3
A. K. Behera responded by saying that even if we use 1.5 x 10 0 (mgst conservative) for the modufe IR, the error in the rNdings is ar module IR.
a suppression pool Since we have at least 90 F margin between'the de:
t nperature and the high high alarm, this small error will still allow the 10 F.
r perator to take corrective action mgch before the suppression pool temper 6 exceed the design temperature of 200 F.
L o.
Aeiorano'ui of Teleanone Conversation Dece cer 1,19g3 E0 of Cunker Ramo / A.phenci Instruments tion projec t M. 8406-18 Penetrations instailec itt LdSalle County COD-041659 Page 6 Unit 2 The NRC :t-#f.;sesticre to: i-t e.e ast "e,onos.as tne ecceptance IR l.; s 1 is acceptsole for LaSalle.
for
'ie instr;1ent "od.le and
..nj, Then A.
Eenera responJec b, sa;,in; tra t the 1.0 x 10 acceptance criteria is for transmitter circuits unich the rost sensitive to leakage IR.
The theruocouples and RID's are mderatel, sensitive to leatace IR.
~
Since the LaSalle application is only limited to therecouples and RTD's the 1.5 x 10' is still acceptable.
Then, the NRC staf f questior,ed regarding this telephone conversation as CECO Then, Mr. A. K. Behera has started a Bunker Ramo Test Program at Wyle Labs.
and S. Hunsader responded with the following:
The test conducted for LaSalle by Bunker Ramo along with the analysis is adequate for the qualification of the subject penetrations at LaSalle.
e The Bunker Ramo test program at Wyle is designed for Byron /Braidwood e
applications.
The test parameters will not envelop the LaSalle DBA environment condition.
c Mr. S. Hunsader summarized the discussion and requested a meeting to discussion the issue further.
The NRC staf f indicated that they understand the LaSalle ap31ication and will review all this data and get back to CECO in five days.
JS:cf L_ __ _ __ _ _
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4 Reference-2.9
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'd UNITED STATES
@ Y,.Ii NUCLE AR REGULATORY COMMISSION 5 (. &l } J/,
wasmNGTON, D. C. 20555 s %-
January 31, 1989 Docket tio.:
50-374 fir, llenry E. Bliss I;uclear Licensing Manager Commonwealth Edison Company P.O. Box 767 Chicago, IL 60690
Dear fir,
Bliss:
SUBJECT:
EliVIR0liMEt1TAL QUALIFICAT10h 0F BUNKER RAl:0 ELECTRICAL PEtlETRAT10ti ASSEMBLIFS AT LASALLE UlllT 2, REQUEST FOR lilFORflAT10tl The purpose of this letter is to describe the staff's findings and. request additional infornlalior regarding the resolution of the issues involving the env'ironmerital qualification of Bunker Ramo containment penetration assemblies installed et LaSalle 'Init 2.
As you are aware, the concern was initially identified during an equipment qualification inspection at Braidwood, Unit 2 in February and March 1988.
Since that tiue, the staff has discussed this problem on numerous occasions with the affected licensees and solicited qualification information from all available sources.
Several months ago the staff requested that each utility, with an cperating reactor (s) that has Bunker Ramo or Amphenol containment penetration assemblies installed, provide a copy of the qualification documentation that demonstrated the qualification status of the assemblies.
The staff completed its review of that information and conclude' that the documentation provided by the licensees was not sufficient to demonstrate geslification in accordance with the reqtiirer:ents of 10 CFR 50.49.
Specifically, for LaSalle Unit 2, the following is a summary review of the documentation you provided in support of EQ for the subject penetrations:
Without additional information regarding IR values recorded during peak LOCA temperatures and the test conditions when the lowest value was recorded, there is insufficient test data and supportirg analysis to demonstrate functional operability of Bunker Ramo penetrations during design basis event conditions.
(Test Report tio. - 123-2183 Rev. 4, February 1982. This test was conducted for LaSalle by Amphenol fiorth America in february 1978).
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,e Henry E. Bliss i j # ^.
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On Aus,ust 4,1988, the staff n,et with representatives of the flucicar Utility Group on Equipment Qualification (NUREQ) to discuss all available qualification information that is applicable to Bunker Ramo /Amphenol Penetration Assemblies.
The objective was to provide industry representatives an additional opportunity to demonstrate qualification.
The meeting also provided the staff with the l
opportunity to discuss available qualification information in a single meeting with representatives from each utility.
HUGEQ presented information in the form of an af fidavit f rom an engineer who participated in conducting environ-mental qualification tests on the penetration assemblies in question during 1977 and 1978.
An important element in the qualification ^of the penetration assemblies is the insulation resistance (IR) which was measured during the first 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> of the testing.
The affidavit recounts that this parameter was ocasured and recorded at least daily during the test in accordance with the test plan.
In addition, the affidhvit recounts that more frequent measurements of this parameter were taken and recorded within the early stages of the test to monitcr concerns regarding the possible flooding of the test chamber.
These latter measurements were apparently nnt made pursuant to the test plan.
The data that was taken to determine if flooding was present could not be located ar.d no test reports presenting these data results are presently available.
However, in his afficcvit, the engineer who was present at the tests recalls that the measurements which were taken and recorded were in the acceptable range and thus demonstrated qualification of the penetration assemblies.
The information available for review including the various test results.of Bunker Emo assernb~ lies which included low IR readings as well.as the affidavit is
} insufficient to demonstrate qualification as required by 10 CFR 50.49.
In addition to the technical inadequacies and questions raised by a review cf this information, the NRC staff is not prepared to accept recollections of events which occurreo in the past as a basis for environmental qualification of these important components.
Memory, especially of events so distant in time, is not a satisf actory substitute for data records made at the time of the test and not in accordance with a test plan.
Further discussions without additional test data are likely to be of little value. The necessary action to establish qualification is to conduct an environmental qualification test as required by 10 CFR 50.49. An acceptable test could be conducted in accordance with the applicable IEEE standard. The tests should be conducted as early as possible.
Replacement with qualified Until the tests 1
penetration assemblies is an alternate approach to testing.
are ccmpleted and evaluated or replacement is completed, the guidance in GL 88-07 to support interim plant operation would be in effect.
You are recuested to furnish, no later than 90 days from the cate of this letter,
/
vour plans and schecule to either qualify, test or repicce the subject I
' penetrations with ones which have been previously demonstrated to be qualified per the licensing criteria applicable to the f acility.
The information is sought to assess your tincly compliante with the current licensing bases fnr your facility.
i l
_ ~,..
a a-lier.ry F. 31iss The reporting and/or recordteeping requirerr,ents contained in this letter affect fewer than 10 respondents; therefore, OMB clearance is not required under Pub.L.96-511.
I Sincerely, Gary tt. Holahan, Acting Director Division of Reactor Projects III, IV, V, and Special Projects Office of Nuclear Reactor Reguletion cc:
See next page.
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Mr. Henry E. Bliss LaSalle County Nuclear Power Station Units 1 & 2 Cou.ir.onwealth Edison Company
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cc:
John W. McCaffrey Phillip P. Steptoe, Esquire Sidley anc Austin Chief, Public Utilities Division 501C One First National Plaza 100 West Randolph Street Chicago, Illinois 60603 Chicago, Illincis 60601 Assistant Attorney Genera'i 100 West Randolph Street Suite 12 Chicago, Illinois 60601 Resident Inspector /LaSalle, NPS U.S. Nuclear Regulatory Coir. mission Rurul Route No. 1 P. O. Box 224 Marseilles, Illir.cis 61341 Chairman LaSalle County Board of Supervisors LaSalle County Courtheuse Ottawa, Illinois 61350 i
Attorney General 500 South 2nd Street Springfield, Illinois 62701 Chairman Illincis Commerce Congnission Leland Building 527 East Capitol Avenue Springfield, Illinois 62706 Mr. Michael C. Parker, Chief Division of Engineering Illinois Departcent of Nuclear Safety 1035 Outer Park Drive, 5th F1cor Springfield, Illinois 62704 P.egional Acn.inistrator, Region III U. S. Nuclear Regulatory Commission 799 Rcosevelt Road, 61dg. e4 Glen Cllyn, Illinois 60137
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UNITED STATES I
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j WASHINoTON, D C. 20666 l
March 15,1989 Docket No.
50-457 Mr. Henry E. Bliss Nuclear Licensing Manager
~ Commonwealth Edison Company Post Gffice Box 757 Chicago, Illinois 60690 1
Dear Mr. Bliss:
SUBJECT:
LICENSE CONDITION OF FACILITY OPERATING LICENSE NPF BRAIDWOOD STATION UNIT.2 - QUALIFICATION OF BUNKER RAMO ELECTRICAL PENETRATIONS-
'The NRC staff has reviewed the Qualification Test Program report on Bunker Ramo instrument penetration assemblies completed for commonwealth Edison Company by WYLE Laboratories.
The purpose.of the qualification program was to verify the ability of the Bunker Ramo electrical penetrations to perform their intended safety-related electrical functions before, during, and after.
environmental qualification tests. The main objective for testing the penetrations was'to demonstrate that the Bunker Ramo Instrument Electrical Penetration Assemblies would maintain their electrical integrit;y throughout plant accident conditions.
After an initial review of the test report, the NRC staff agrees with the licensee's conclusion that based on the test results provided in the, test report, the Bunker Ramo Instrument Electrical Penetration Assemblies are environmentally qualified to perform their intended functions. license condition of Therefore
. temporary exemption from the requirements of 10 CFR 50.49(f) and 50.49(j) has been satisfied since testing of the equipment with supporting analysis was provided and did show the equipment to be qualified. A detailed staff review 1
i of the report is continuing and any future concerns will be identified subsequently.
Sincerely, Daniel R. Muller, Director Project Directorate III-2 DivisionofReactorProjects'-III, IV, y, and Special Projects cc: See next page Li o
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