ML20072E542

Responses to Fourth Set of Interrogatories & Request for Production of Documents.Related Correspondence

ML20072E542
Person / Time
Site:	Perry
Issue date:	06/21/1983
From:	Hiatt S OHIO CITIZENS FOR RESPONSIBLE ENERGY
To:	CLEVELAND ELECTRIC ILLUMINATING CO.
Shared Package
ML20072E545	List: ML20072E542 ML20072E552
References
NUDOCS 8306270014
Download: ML20072E542 (5)

Text

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l UNITED STATES OF AMERICA 4 0 7['i__ , , ..

'_._ NUCLEAR REGULATORY COMMISSION hlh  %

T6: *r'~ Before the A$omic Safety and Licensing BoarcN

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3,.p l4 fw',In the Matter of

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. 7.hd5'b. '. ObblE'SRESPONSESTOAPPLICANTS' INTERROGATORIES AND M$9 T REQUEST FOR PRODUCTION OF DOCUMENTS (FOURTH SET)

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[$ [ 1-3.' M RE will defer answering these interrogatories pending the

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'j;!: ', appraisal of.the referenced documents by consultants

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69 ~ possessing expertise in these matters.

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3 [ Issue'#i[ In-Core Thermocouples

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{i ' 4. (a)~ The thermocouple range of 200-23000F is based on Regulatory Guide 1.97, Revision 2, Table 1, wherein this range is specified.

SO F was a judgement of an

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(b) The stated accuracy of 2 acc'eptable accuracy. Since the thermocouples now suggested by OCRE (see "OCRE's Supplemental Response to Applicants '

[g Third Set of Interrogatories") appeat to be more accurate z .

. than, this '(calibration tables of temperature vs. output voltage in the reference cited indicate resolution to 1 F -

1 throughout the -300 to 2500 F range), the point is moot.

5. As stated in OCRE's response to Interrogatory 15c .(Applicants' Third Set), OCRE'has not formally analyzed the exact numbers

! and locations of thermocouples. The basis for the statement quoted in this interrogatory is that the 41 thermocouples in l

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would provilde~t'he maximum available

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-.,eyMy# W,' coverage - - - . ate.that v axial.. height for detecting inadequate core m,.;,a. s,4p%&.W:i., - * . ~. .p'

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JV.WWcooling,'. core uncovery, .or. local.tzed hot spots (e . g . , fuel

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,i-ZO uhdle'  : nblockage) i,: The remaining.12 tihermocouples '(3.per

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-a quadrant)L ~ wo,uld.'s'erve this function at another axial' height

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nMdia:in .the c6rei .ther'eby alerting operators tos further uncovery T5&.At -

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wmic3  :-En.e.f ;J1c E - zoffthe s . core. -

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.5ES.d.ite.c.r.t*T,he s> p. n n:-. .n-g- numbers..given were merely an example of an acceptable fiQiCM Wy~.,idW:.x . -

h.f/2ES2 W W .#h- 'sfstem. x. ,- s Using all LPRM locations (164) would provide even

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.;gny , ;.6D (a)& The.GE Evaluation of'the Need for In-Core Thermocouples 4.h .

Y.$ril}9QQ. 'si/;31nc.BWRs , ~ Section .l. 0, . states .that "the most practical

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QFdf::,ilocation..to 72- ~ P 'JM ~ install 'in-core thermocouples in. a BWR is in

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[ All other locations would require additional penetrations and

_ major redesign of the . vessel internals and/or the fuel bundles."

OCRE does not accept this premise because this statement

. ',; 3 9.hb99,does not contain or reference any supporting' evidence to

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'C ~(b). Since OCRE has not conducted research into this matter,

{no such locations have been identified.

7. (.a)='Although: experiments conducted in a fueled. reactor would -

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6oth with respect to in-core thermocouples and to general unresolved questions on reactor safety, safety hazards would 5 probably preclude this. In any event, such experiments should not be conducted on the PNPP reactors because of the hazard

, to public safety. Rather, if experiments are to be conducted

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32.'. Nf UEd,.;z jFor'the experiments suggested by OCRE with regard to

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1. fin-core thermocouples,.a simul.ated. reactor with fuel rods ry , p-@dT;;p .

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. . , ' h'eated. electrically would be sufficient. Such a test reactor Q .,c,brI Q iddould faithfully simulate the geometry of a BWR, with respect

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WWsyM.M3Ytcifuel . s. e.ppq,6 bundles, . control rods, steam separators,. steam dryers,

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}tipical of BWR' operation, have recirculation-loops and jet y.;..

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_cpumps, safety-relief valves,. and be capable of simulating a .

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r various transient and LOCA1 conditions, as.well as typical core

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. power-levels.throughout the core. Variables to be measured

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.-x.~.. vessel water level, fuel cladding temperature (with

,c-thermocouples affixed to the cladding), and thermocouple

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response, with thermocouples located in the LPRM thimbles or other possible locations.

(b) The. general methodology for such experiments would involve measuring in-core thermocouple response, fuel cladding temperature, and reactor water level in response to various simulated accident conditions suggested below. Detailed examination of the fuel rod cladding after each accident simulation could provide confirmatory information on temperatures reached.

The data generated would confirm whether or-not in-core thermocouples provide useful, timely, and unambiguous infor-mation, and cot $1d provide a basis for possible charts, graphs, or computer programs which could aid operators in interpreting thermocouple response.

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loss ~of boolant inventory and/or. insertion of m;T;n.,

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<*.2:ip:. . O. .;P, s. reactivity, including but n'ot necessarily limited to the' A.-d:. . litwt+c '. .

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_ the'best available data and calculations, including those I

_c.c-._of the NRC and independent analysts. Since'OCRE has not 1

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The accident conditions identified above were chosen because.they represent (1) situations in which reliance is placed primarily on level measurement (in-core thermocouples here serving as a redundant and diverse indication of water level);  ?(2) situations in whi~ch the usefulness of in-

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core thermocouples has been' questioned (during ECCS operation and SRV opening); and (3) conditions which would not be

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det,ected by existing instrumentation (localized heating, such as. fuel bundle blockage).

(d) The experiments-described above are the same as the

" experimentation" referred to in OCRE's response to Inter-roga. tory #17 of. Applicants' Third Set of Interrogatories.

i (e) Not applicable.

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(a)LAll~

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relied upon.are identified.in.the responses.

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f(b)f No such'.persong.have been identified.

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-Q.9.$ Applicants- in' their response to OCRE's Interrogatory 9-34

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'....' ..f' i state (.that MSIV. leakage will be detected by Type C tests

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, C,-? (5ie~e Appendix'. J . to 10 CFR ' S 5 0) .

t OCRE considers this

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. general methodology appropriate, if the tests are conducted

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'c. C . ...Q.with sufficient frequency. >

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,"O 75 IE Information Notice 82-23' states that the NRC is r u,g.,y _

considering the need for, inter alia, more frequent MSIV testing. This would seem prudent, given that the testing y

programs of the,other licensees had.. failed to detect MSIV leakages in excess of;3000 scfm until the regularly scheduled

' testing intervals. .

10. ' ('a ) All documents relied.upon are identified in the response.

(b) No such persons have been identified.

Gener&l.-Interrogatories 11-14. The relevant information requested is provided in the athached affidavit.

Respectfully submitted, 4nWb Susan L. Hiatt OCRE Representative 8275 Munson Rd.

Mentor, OH 44060 (216) 255-3158 s

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