ML19321A371

FOIA Request for 20 Documents for Use as Intervenor in Facility Proceeding

ML19321A371
Person / Time
Site:	05000467, Allens Creek  File:Houston Lighting and Power Company icon.png
Issue date:	06/27/1980
From:	Doherty J DOHERTY, J.F.
To:	Felton J NRC OFFICE OF ADMINISTRATION (ADM)
References
FOIA-80-335 NUDOCS 8007230246
Download: ML19321A371 (4)

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, J' FREEDOM OF tt4 FORMAT 10N June 27, 1933 ACI REQUf*SI -

porA-go-335' 4327 Alconbury Lano #3

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Houston, Texas 77021 J. M. Felton, Director Division of Rules and Records i

Office of A:1 ministration U. 3. IIuclenr Ec.7,ulatory Conlission

'das'Tincton D. C.

Dear Mr. Felton,

Enclosed is an FOIA recuest, which I am filinr in accord-ance with your let;er of Harch 3, 1980, setting a reduce 9 co?~ing charre, and which was in recponse to EOIA 80-3, 30-3 and 83 47.

I most recently roccived FOIA 80-289 As in previous retusts I have attempt 3d to enclose docket number and NRC accession numbers to assist identification.

Most of the are Licencee Zvont Reorts of short length.

As before, I have not a~ ransons for the request and identi-Tied the relevant ca2tention for the Allens Creek proceeding.

~_ han': you very much.

S'ncerely Sh,J C

/dohn F. Doherty 80072304UYlk

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1. Letter from E.

D. l'u iler (G. E. ) to D.

F. Ross(iiRC), of 1/13/73

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Code described here is sited as identical to "TafGLS-2".

In my contention,,215, I have asserted WIGLE code is inaicquate to represent a power excursion neutronics in a ome dimensional code.

This letter is ianortant, becauce staff asserts comparisons in t'o letter demonstrate a one a

dimensional code is coascrvative uith res"ect to a three dimensional code.

2. Letter fron G.G. Sherwood of Gen;ral Electire to D. EisenSut (ERC) of 3/'9/79, which ci', :s inforuntion on the influence of the Doppler effect on Zuel Rod 3 mia;.

This letter is necied, because ay Contention.333 asserts Dop'ler han been overestinated as a significant check on reactivity;iuring core distorting nccidents, and my co.tention 13 ascerts fuel rod boring is a likely accidant result in case of reactivity insertion due to nelting of fuel and stcaa explosions or metal-vater rescbions uhen nolten fuel strikes coolant.

This is,the on17 301rce from bhe manufacturer of bhe Allons Creek reacbor to even acation fuel rod bowing and hence is imporbant to shou'from their oun ro.; arks that bowine is a nossibility.

It also a, pears the Doppler inadequapy argu-ae'nt of this intervenor will be ai'ressed here.

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3. Docket 5J-373/374 LaSalle Station, Unit 1 t 2. Cection 15.h.4.2 of the FSAR (Aa,,335 is part of tnis, 7/78).

Staff, in reply to an interrogatory to my Contention #^6 referenced this.

This material is needed to refute their atte"pt to show start-ups of the i,11 ens Creek plant at high xenan concentrations and at low or no void canditions do not recuire prohibition because copsequences of continuous with'rawal of high rod worth are shown accontable in this accident anal.vsis.

4; From the list of documents relating to the 1064-65 re-axanination of NASH-740 (URC document), in Fublic Document Room, docket number 144-18, on pace 12, a meno from C.H. Ecck to the Atomic Energy Comaission on the draft report to the Joint Comaittee on Atomic Enercy on the 1965 restudy of NAGH-740, a list of reactors on which stud bolts have broken.

This list':(should be cuite short) is needed to chow the extent of stud bolt failure in 07erating recctors.

At the moment the only definite failure evilence I have is froa the LaCrocce BUR, which was provided ass 0-134/18.

5. Dociet 50-249, bresden-3, 3. 3. Stephencou (Commonwealth Edison),

Letter to James G. Kapoler (UEC), Follou Up Report to Abnormal Occurence Entitle " Correlation of Fuel Pailures at Dresden-3 Identified by Vet Si oing Tests to Calculated Violation of GE PCIOMR, June ?0 1975. Reason needed: General 3lectric has croposed a 15 p,lastoi str1in criterion for zironiume dlad should serve as the pellet-clad int raction dama:e linit.

Houever, this report shows pellet-clad interaction of less than 15 has been observed to occur at plastic strains less than 1%.

In my contention 8, regarding ATWS, I will need to show that the public is not adequately protected against the several fuel cochaaical actions, such as fuel swelling uhich leads to pellet clad interaction in this accident type.

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, bh. Docket'50-P78 Peach Botton Station,. Unit III.,LER S0-001/03L-0.

Failure of nain stean line aonitrr.

Uccded for Doherty Contention 514, which asserts this system is not adequate uhen rraning corroctly.

Seeded to find out if.MSLRM was inoperative for considerable time before defect discovered on surveilance test.

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15. Docke't-50-2G5 hund Citi es Unit II. LER 80-01/03L-0. Colief.

valves stick' shut beyond setting during testing.

" ceded because Doherty-Contention #17 asserts that valves may stick, then open at higher pressure resulting in suppression pool danace.(8002220404)

16. Doc %et 50-271 Vermont Ynnice.

LER 80-004/03L-0. Power supply overheat-caused failure of rod pattern information system and rod drift alarm.

Ucedel for Doherty-12, which Will try to show the analogous system in Allons Creek endan[;ers the public because of several failures such as these.

17. "Hydroten Generation & Prasuro puppr2ssi n Containments" 7-pace doc., 3002140110 by Kasteaberg of ACES. Uceded for Doherty Contention 19, that loads including hydrogen ignition loads cannot be withstood by the standing steel shell, the lover portion of which is the suppression pool in the Mark-III design of Allens Creek.

18. Portion of Transcript of ECCS/ Reactor Fuels' Subcommittee aceting in h*ashington D. C. of Advisory Comaittee on Reactor Gefeguards of Feb..SE, 1930 which is devoted to fuels for Water Reactors.

This would be General Electric Fuels.

This is needed for Doherty Contention #39 on fuel clad swelling and rupture,-because it probably makes a direct statenent on the adequacy of this fuel vendor's product, and is likely to be Houston Lighting & Power Company's essential case.

19. Research Inforaation Letter 78, vertical loads in Mark-I containment tcrus-during air ventinc phase of 10CA. This doc-l ument of'7 paces anpears useful to better understanding the offects of air clearing phase relevant to Doherty Oon. #5 that swellinC of the suppression pool endangers overhead structures, and that pressure from blowdown to the suppression pool, inclu-ding such air chases is a hazard (Doherty #17). 8002260236.

20. Transcrint of Feb 13, 1980 ne:.tinc of Commission (8002200556) re: tur'oin missiles.

Hee'ed for Doherty Cont.,#47 that turbine nissiles and-effects of lost turbine balance cause a hazard to la7ediate safe olant operation. (54 pages)

21. 8002207274 (TCFREP) Calculation of crack 7rowth rate for keyway template in turbine discs. Reeded for Doherty #47, because the calculation of crack crowth rate will largely determine the in7ortance Hof this contention..

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-(2) s part of demonstrating this langer, I need to show-the acceptable criteria recoaacnied by the Allens Creek reactor aanufacturer is not adequate to AT'd3 conditions.

This report appears from P.8 of Docudent A-36 of your previous corresponf ance to indicate that.

6. Docket 0-333, James A Fitzpatrick plant. LER 80-001/03L-0, AFRH lownscale trip inexact due to drift.

!! ceded to show unreliability of this cystme for Contention 812, Jthe RCIS vhich depends on APRM to initiate rod block, which this intervenor says is unreliabile (8002010336 and 8002G1338.

7. Dociet CO-333, James A. Fitzpatrick plant. LER80-012/03L-0 Emer,:ency renerator failed due to oil heater failure, lieeded to show these units are unreliable despite improvements, in Doherty. Contention $10. (8002140712 and 8302140707.

8. Docket 50-333 James A. Fitznatrick plant. LER30-013/03L-0 On testin7, lo-lo-lo 1cyc1 switch failed.

I'eeded to show as in Dohert7 Contantion 41, redun-lant as to type and function water level indicators should be installed at ACliGS (8002200558)

9. P.c': t 7 2 059 3ec.c "crry, U;1t 1. 121 00 01':/031-0, failt;e

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c m uleser level c; itch.

9hk ia-n;;,2.0 50 shw..

ea in'e"I "32Aat tho_.lo-v.al-snther,-in--the r' *" dischug-e v;1 ad are cubject t: Rilarc,

.1_ h t '... mili'i is 2,si..o is n_t-s'.

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10. Docket 50-259 Browns Ferry, Unit 1. LER 80-008/03L-0.

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Crack in coupling bearing support pedestal on HPCI turbine.

due to water hammer (?).

TVA has raised possibility of water hammer danage here, as has this Intervenor in his Contention 44 This LER will be used to show water hancer may damage vital plant systems at ACHGS as allered.

11 Docket 50-321 Edwin Hatch "uclear Plant Unit 1.

LER 80-10/03L-0.

Failura due to sat point drift of: standby liquid control system discharco valve. Relvent to Doherty Contesnion 38, which asserts their is dancer froa anticipated transients without SCRAM, for uhich the standby liruid control system was designed.

Furthers Intervenor's posi) ion the system is n6t adequate (8002220419 and forwarding letter (8002220419)

12. Docket '0-P20, Nine Mile Point, Unit 1. LER 80-005,/01X-0 Enginoering eval of lo-lo set point of reactor water level recuires change of 20". Relevant to Doherty Contention y41, that detection of low level in reactor core may be defective in various ways and that redundnnt indicators are hence required.

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13. Docket rO-??? Feach 30ttra II. LER'SO-004/03L--0. Rod Block Monitor electronic circuit failure.

The Rod Block nonitor is succeeded in part by the rod control and information system in the Allens Creek plant.

This L2R is needed to show the electronic t

nortion of the system is subject to failure ~. (S002230473).

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