ML19323D891

Responds to 800405 FOIA Request & Provides Further Response to Seven Earlier Requests for Documents Identified by Accession & Rept Numbers,Author & Description.Forwards Documents Listed in App A.W/O Encls

ML19323D891
Person / Time
Site:	Allens Creek File:Houston Lighting and Power Company icon.png
Issue date:	05/14/1980
From:	Felton J NRC OFFICE OF ADMINISTRATION (ADM)
To:	Doherty J DOHERTY, J.F.
References
FOIA-80-118, FOIA-80-134, FOIA-80-159, FOIA-80-185, FOIA-80-3, FOIA-80-47, FOIA-80-8 NUDOCS 8005220480
Download: ML19323D891 (21)

Text

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UfJITED STATES j

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NUCLEAR REGULATORY COMMISSION N/M CA{

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E WASHINGTON, D. C. 20555 o

%... pE May 14, 1980 Mr. John Doherty 4327 Alconbury Lane #3 IN RESPONSE REFER TO Houston, TX 77021 F0IA-80-3, 80-8, 80-47,80-118 80-134,80-159 & 80-185

Dear Mr. Doherty:

This is in reply to your letter dated April 5,1980, and also in further reply to your seven earlier letters submitted under the case numbers stated above.

In all of your letters you requested, pursuant to the Freedom df Information Act, copies of documents which you listed and specifically identified by Accession Number, Report Number, Author, number of pages, and brief description.

In further response to your seven requests, the documents listed in Appendix A are enclosed.

Our search is continuing for the documents listed in Appendix B, and we will communicate further with you concerning those documents.

With regard to your previous requests, you were granted a waiver of 75%

of the fees involved based upon your representation of lack of ability to pay the full amount and your status as an intervenor in the Allens Creek proceeding.

However, waivers such as the one granted you are made on a request-by-request basis.

As you are aware, 10 CFR 59.14a(g) provides that the NRC will not waive fees for documents which are available in the public document room absent a compelling reason to do so.

Frankly, given the voluminous nature of your document requests, it is unclear to us that there is a compelling reason for a continued waiver wi'th regard to the documents i

you request.

Of course, should a particular document be necessary for the preparation of your case, we would deem that to be a compelling reason to continue the waiver of 75% of the fees involved.

Therefore, while we will provide the documents you have requested to date in accordance with our previous understanding, no 75% waiver of fees will be granted in the future unless the document request is accompanied by an explanation as to why each document sought is necessary to the preparation of your case on a particular issue which you have proffered for consideration b'y the Licensing Board.

In the absence of such an explanation, the documents requested will be provided at a cost of $0.08 per page.

' ' 80 06 220 l((SO

i For the 1,999 pages of documents enclosed, please send a check in the amount of $50.00 payable to the "U.S. Nuclear Regulatory Commission" along with a copy of this letter, to the Director, Divisien of Rules and Records, MNBB-42.0, U.S. Nuclear Regulatory Comission, Washington, DC 20555.

Sincerely, gY

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J. M. Felton, Director Division of Rules and Records Office of Administration

Enclosures:

As stated e

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N F01A-80-8

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F01 A-80 47 F01A-60-134 APPENDIX A F0IA-80-159 F01A-80-185 F01A-60-118 HRC F0!A NUMBER DOHERTY t.IST NUMBER NRC ACCESSION NUMBER DOCUMENT DATE TYPE OF DOCUMENT PAGES 1.

80-3 5

7706290175 3/7/79 MINUTES OF THE ACRS 20 SUBCOMMITTEE ON ECCS 2.

80-3 12 7904050074 2/13/79 INTERIM REPORT-LETTER 2

3.

80-3 16, 7909270564 7/79 BWR BD/ECC PROGRAM 6

FORTY-FIFTH MONTHLY REPORT 16 7909270564 4/79 INTERIM REPORT-LETTER 10

• 4.

80-3 5.

80'3 19 790702b465 1/31/79 MINUTES OF THE ACRS 38 SUBCOMMITTEE MEETING ON ANTICIPATED TRANSIENTS

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WITHOUT SCRAM 6

80-8 9

7901290330 1/19/79 MEMORANDUM FOR: K. KNIEL 21

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FROM: M. TOKAR

SUBJECT:

MEETING

SUMMARY

7 80-47 1

7906060168 5/31/79 IE Bulletin No. 79-12 8

SHORT PERIOD SCRAMS AT BWR FACILITIES L.

g F01A-80-8 F01 A-80-47 F01A-80-134 APPENDIX A FOIA-80-159 F0IA-80-185 FOIA-80-118 NRC FOIA NUMBER DOHERTY LIST NUMBER NRC ACCESSION NUMBER DOCUMENT DATE TYPE OF DOCUMENT PAGES 8

80-47 2

7903060570 1/22/79 NOTE FOR: D. EISENHUT 1

FROM: B. BUCKLEY

SUBJECT:

STEAM GENERATOR WATERHAMMER SCHEDULE 9

80-47 3-7903070261 2/1/79 LETiER RE: RECIRCULATION 4

INLET SAFE ENDS 10 80-47 4

7903130255 2/12/79 MONTHLY STATUS REPORT 14 11 80-47

.5 7903134 58 2/22/79 LETTERS RE: MEETING ON 5

DRAFT REPORT FROM INEL 12'. 80-47 5

790310568 3/29/79 ENCLOSURE 1 MEETING 137 AGENDA - ENCLOSURE 2 BRANCli TECHNICAL POSITION 4.2.1 13 80-47 6

7903140630 2/21/79 NOTE WITH ENCLOSURE 17

SUBJECT:

COMMENTS BY L. CAVE ON WASH-1400 14 80-47 7

7903150002 2/9/79 Contract No. NRC-04 10 215 INFORMAL' MONTHLY PROGRESS REPORT

F0!A-80-8 F01 A-80-47 01A-80-134 APPENDIX A F01 A-80-159 F01A-80-185 F01A-80-ll8 URC FOIA NUMBER DOHERTY 1.IST NUMBER NRC ACCESSION NUMBER DOCUMENT DATE TYPE OF DOCUMENT _.

PAGES 15 80-47 8

7903200297 3/1/79 MEMORANDUM RE: RESPONSES 24 TO ATWS QUESTIONS 16, 80-47 9

7903300595

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3/7/79-REACTOR COOLANT PbMP 4

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OVERSPEED PREDICTIONS FOR COMBUSTION ENGINEERING SYSTEM 80 17 80-47 10 7909050232 2/8/79 POTENTIAL EXPLOSIVE GAS 4

MIXTURE ACCUMULATIONS ASSOCIATED WTTH BWR OFFGAS SYSTEM OPERATIONS 18,. 80-47 11 790711bl57 5/18/79 MEMORANDUM RE: SAFETY 43 AND RELIEF VALVES WITH ENCLOSURES 19 80-47 11 7907110157 5/18/79 MEMORANDUM RE: SAFETY 48 AND RELIEF VALVES WITH ENCLOSURES 20 80-134 3

7812040134 11/1/78 DC POWER SOURCE FAILURE 22 FOR BWR/3 AND 4 21 80-134 4

3/3/75 REGULATORY BRIEFING ON 11 DRESDEN 3 WITH THREE ENCLOSURES

RE F FOIATE053 F01A-80-8 F01 A-80-47 FOI A-80-134 APPENDIX A r01 A-80-159

'F01A-80-185 F01A-80-118 NRC F0!A NUMBER DOHERTY LIST NUMBER NRC ACCESSION NUMBER DOCUMENT DATE TYPE OF DOCUMENT PAGES 22 80-134 5

1/17/75 REPORT OF ABNORMAL 4

OCCURRENCE PER SECTION 6.6.A 0F TECHNICAL SPECIFICATION - 0FF GAS HIGH RADIATION ON UNIT 3

23.80-134 6

5/22/75 LETTER RE: ABNORMAL 6

OCCURRENCE AS REQUIRED BY TECHNICAL SPECIFICATION 6.6.B.1. WITH ENCLOSURE

'24.80-134

,7 7911280325 10/79 MONTHLY PROGRESS REPORT 9

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7/21/78 OUTSTANDING SAFETY REVIEW 21 25,80-134 8

ISSUES - ALLENS CREEK

26.80-134 9

4/14/78 REQUEST FOR SUPPLEMENTAL 13 INFORMATION - ALLENS CREEK LETTER WITH ENCLOSURE

27.80-134 10 7901150079 12/22/78 FAST SCRAM CRD DESIGN 6

VERIFICATION 28 80-134 10 7901150084 10/78 FAST SCRAM CONTROL R0D 76 DRIVE QUALIFICATION PROGRAM l

0

F01A-80-8 F01 A-BO-47

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01 A-80-134 )

APPENDIX A F0I A-80-159 I F01A-80-185 i FOIA-80-118 i NRC FOI A NUMBER DOHERTY LIST NUMBER NRC ACCESSION NUMBER DOCUMENT DATE TYPE OF DOCUMENT PAGES 29 80-134 11 3/22/74 LETTER WITH ENCLOSURE:

7 MODIFIE0 GE MODEL FOR FUEL DENSIFICATION 30 80-134 12,

7904170257 4/10/79 SOLEN 0ID VALVE ENDURANCE 24 TESY - NEDE 24611 LETTER e WITH ENCLOSURE 31 80-134 13 7907180916 6/4/73 REQUEST FOR ADDITIONAL 9

INFORMATION REGARDING SMALL' BREAK LOCA ANALYSIS 32 80-134 14 7907240443 6/2/79

SUMMARY

OF MEETING WITH 86 GENERAL ELECTRIC 33.'80-134 15 7909110005 7/26/79 RESPONSE TO IE BULLETIN 3

No. 79-12 34 80-134 16 7909280041 7/30/79 TVA's RESPONSE TO OIE 5

BULLETIN 79-12 SHORT PERIOD SCRAMS AT BWR FACILITIES 35 80-134 17 7909280045 7/30/79 MONTICELLO NUQLEAR POWER 2

PLANT L

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RE!

F0!A-80-3 F0!A-80-8 F01 A-80-17 F01A-80-134 APPENDIX A FOIA-80-159 F01A-80-185 F01A-80-118 flRC FOIA riUMBER DOHERTY LIST NUMBER NRC ACCESSION NUMBER' 00Cb.'iENT DATE TYPE OF DOCUMENT PAGES 36 80-134 18 12/71 AN INVESTIGATION OF THE 80 FAILURES OF LACBWR PRESSURE VESSEL CLOSURES STUDS 37 80-159 1

7912060521 11/16N9 GE CLADDING H00P STRESS 13 AT PERFORATION 38L 80-159 2'

7912180151 12/6/79 LETTER AND APPENDIX RE:

2 USE OF HIGHER FUEL BURNUPS IN COMMERCIAL LIGHTWATER NUCLEAR REACTORS 39,80-159 3

7912190568 12/14/79 BWR CAPABILITY TO ACCOMM0- 19 DATE ATWS 40,80-159 4

7912190599 12/7/79 COMMENTS ON THE DRAFT REPORT 8 NUREG 0630 41,80-159 5

7912200381 12/12/79 REQUEST FOR ADDITIONAL 3

INFORMATION ON GE REPORT NED0-23652

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42.80-159 6

791220038 11/27/79 CONTROL R0D DRIVE RETURN 6

LINE REMOVAL'-

RE:

F0!A:80-3 F0!A-80-8 F01 A-80-17 F01A-80-134 APPENDIX A F0IA-80-159 F01A-80-185

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F0lA-80'll8 NRC F0!A NUMBER DOHERTY LIST NUMBER NRC ACCESSION NUMBER DOCUMENT DATE TYPE OF DOCUMENT PAGES 43 80-159 7

7912270292 12/18/79 PRETEST PREDICTION OF 15 TLTA SMALL BREAK TEST I 44 80-159 8

7912110104 4/5/79-TVA COMMENTS ON REGULATORY 2

GUIDE 1.9 45 80-159 9,

7912180462 5/8/79 ZIRCALOY AND STAINLESS STEEL 1 AS CLADDING MATERIAL IN LIGHT WATER REACTORS

'46 80-159 '

10 8002220259 12/10/79 LETTER T0: CONGRESSMAN 6

UDALL FROM: MAX W. CARBON, CHAIRMAN 47 80-159 11 7912270114 11/15/79 NRC RESPONSIBILITY TO 2

ALLEVIATE RESIDUAL FEARS 0F TMI-2 AREA RESIDENTS 48 80-159 12 7912050100 11/16/,79 LOSS OF 0FFSITE POWER SURVEY 4 49 80-159 13 7912180457 5/9/79 0YSTER CREEK TRANSIENT 16 RESULTING IN LOW CORE WATER LEVEL ED e

RE:

F0!A-80-3 F01A-80-8 F0! A-00-47 APPENDIX A F01A-80-134 F01 A-80-159 F01A-20-485 F0IA-80-116 NRC FOIA NUMBER DOHERTY LIST NUMBER NRC ACCESSION NUMBER DOCUMENT DATE TYPE OF DOCUMENT PAGES 50,80-159

,15 7912140506 11/9/77 MEM0 WITH TWO ENCLOSURES 7

ON RESEARCH INFORMATION LETTER #14

" PHYSICAL SEPARATION CRITERIA FOR ELECTRICAL CABLE TRAYS 5;.80-159 14,

7912140514 5/5/78 RESEARCH INFORMATION LETTER 22

1. 17 - POWER BURST FACILITY (PBF) SINGLE R00 POWER-COOLING MISMATCH (PCM) TEST RESULTS -

i MEMORANDUM WITH ENCLOSURES

52.80-159

.16 7912060364 11/8/79 POTENTIAL FAILURE OF 3

EMERGENCY DIESEL GENERATOR FIELD EXCITER TRANSFORMER -

LETTER WITH ATTACHMENT

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53,80-159 17 7912100407 11/2/79 LETTER WITH ATTACHMENT RE:

9 EFFECT OF NEW R0D BURST DATA ON ENC FUEL MODELS 54,80-159 18 7912100456 11/4/79 LETTER WITH ATTACHMENT 22 RE: RECENT R00 BURST DATA REVIEW

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55.80-159 19 7912180 12/6/79 LICENSEE EVENT REPORT 1

Nt,i U g I A=,c g,J FOIA-30-8 F 01 A-80-17 F01A-80-134 APPENDIX A F0IA-80-159 F01A-80-la5 F01A-80-118 URC F0IA NUMBER DOHERTY LIST NUMBER NRC ACCESSION NUMBER DOCUMENT DATE TYPE OF DOCUMENT PAGES 56 80-159 20 7912270301 12/7/79 LICENSEE EVENT REPORT 1

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57 80-159 21 7902080313 12/15/78 LETTER AND VOLUMES 1 403 AND 2 NONPROPRIETARY VERSION, NED0-24154 58 80-159 22, 7909110005 7/24/79 RESPONSE TO IE BULLETIN 3

No. 79-12 5'9 80-159 23 7909280041 7/1/79 LETTER WITH ENCLOSURE 4

RE: I&E BULLETIN 79-12 60,.80-159 24 790928b045 7/30/79 LETTER T0: J. KEPPLER 2

FROM: L. J. WACHTER RE: MONTICELLO NUCLEAR GENERATING PLANT

61.80-185 1

7912180090 11/20/79 PRELIMINARY NOTIFICATION 1

CRACKS IN LOW PRESSURE TURBINE DISKS 62 80-185 2

7912140427 7/24/74 PRELIMINARY TEST RESULTS 4

FOR HEAVY SECTION STEEL TECHNOLOGY INTERMEDIATE TEST VESSEL V-7 i..

i

Mt.1 PUJArbusJ F01A-80-8 F01 A-80-47 FOIA-00-134 APPENDIX A F0IA-80-159 F0!A-80-185 F0IA-80-118 HRC FOIA NUMBER DOHERTY LIST NUMBER NRC ACCESSION NUMBER DOCUMENT DATE TYPE OF DOCUMENT PAGES 63 80-185 3

7012140475 2/25/77 MEMORANDUM RE: RESEARCH 3

INFORMATION LETTER - 10, PRESSURE VESSEL FAILURE PROBABILITY PREDICTION 64.80-185 4'

7912140509 12/1/77 RESEARCH INFORMATION 4

LETTER - #15 - CHARACTERIZA-TION OF BWR FEEDWATER N0ZZLE CORNER CRACKS 6 5'.80-185 5

7912190639 12/10/79 LETTER T0: R. DENISE 7

FROM: G. F. 0WSLEY RE:

REVIEW 0F DRAFT REPORT

66.80-185 6

7912270546 12/4/7h LETTER T0: RICHARD DENISE 1

FROM: T. M. ANDERSON RE:

DESIGN APPROACH FOR FUEL PELLET / CLAD INTERACTION

67. 80-18fi 7

7912310188 12/12/79 LETTER WITH ENCLOSURES RE:

6 STAFF POSITION ON WATER SHIELDS 8

7911210433 11/2/79 BRIEFING ON SWELLING 0F 64 66.'80-185 FUEL CLADDING - RESULTS OF RESEAROi & ACTIONS BEING TAKEN - PUBLIC MEETING

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F01A-80-8 F01 A-80-47 F0IA-80-134 APPENDIX A F0IA-80-159 F01A-80-1S5 F01A-80'118 URC FOIA NUMBER DOHERT( LIST NUMBER NRC ACCESSION NUMBER DOCUMENT DATE TYPE OF DOCUMENT PAGES 69 80-185 9

7911200079 6/25/79 RESULTS OF.THE ACRS 20 SUBCOMMITTEE MEETING ON RELIABILITY AND PROBABILISTIC ASSESSMENT.-

70 80-185 10' 7908130280 7/6/79 LETTER T0: DR. YELLIN 2

FROM: D. R. MULLER RE:

ADDITIONAL COMMENTS ON PAPER 71 80-185 11 7908130284 5/29/79 LETTER T0: D. F. BUNCH 2

FROM: J0EL YELLIN 7911025178 10/24/79 INTERIM REPORT PROGRESS 4

72,..80-185 12 REPORTED FOR AUGUST 1979 73 80-185 13 7911090315 4/79 CODE ASSESSMENT AND 115 APPLICATIONS REPORT THERMAL ANALYSIS BRANCH 74 80-185 14 7911210428 10/79 INTERNAL TECHNICAL REFORT 20

75.80-185 15 7911090556 Undated EVALUATION OF THE EFFECTS 45 0F CORROSION PARTICLES ON CONTROL R0D 'DPlVE OPERATION GENERAL ELECTRIC REPORT

F0!A-80-8 F01 A-80-4 7 F01A-80-134 APPENDIX A FOIA-80-159 -

F01A-80-185 F01A-80'll8 URC FOIA NUMBER DOHERTY LIST NUMBER NRC ACCESSION NUMBER DOCUMENT DATE TYPE OF DOCUMENT PAGES 76 80-185 16 7911080324 10/29/79 LETTER RE: USE OF THE 7

SQUARE-ROOT-SUM 0F THE SQUARE (SRSS) METHOD FOR COMPUTING MULTIPLE DYNAMIC LOADS.

77.80-185 17 7911150012 10/31/79 LETTER TO V. ESPOSITO 3

FROM: R. P. DENISE RE:

CORRELATIONS FOR RUPTURE TEMPERATURE, RUPTURE STRAIN, AND ASSEMBLY FLOW BLOCKAGE

78.80-118 1

7911260073 5/15/79 MEMO.T0 D.F. ROSS FROM 3

S. THADANI

SUBJECT:

STUCK OPEN

"~'

p0WER OPERATED RELIEF VALVE AT FORElGN'PWR

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79.80-118 2

7911210015 10/15/79 LETTER TO ROSS'A. SCARAND 1

FROM WALLACE N. MAYS 80.80-118 i.

7911200027 8/24/.79 LETTdRTOG.R. DAVIS 2

FROM ROSS A. SCARAND

81.80-118 4

7911120271 ORDER BY SAFETY AND LICENSING 3 BOARD

82. '80-118 5

7911270013 10/17/79 TO ALL OPERATING. NUCLEAR 3

PDWER PLANTS FROM DARRELL G EISENHUT t

ret FolA=80"3 i

F01A-80-8

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FCIA-80-47 l F0!A-80-134 !

APPENDIX A F01A-80-159 !

F01A-80-185 F01A-80-118 t

.~

HRC FO!A NUM8ER DOHERTY 1.IST NUMBER NRC ACCESSION NUM8ER DOCUMENT DATE TYPE OF DOCUMENT PAGES 83.80-118 6

7911290157 11/16/79 STROKE TIMES FOR PONER 2

OPERATED. RELIEF VALVES

84.80-118 7

7911150446 10/30/79 MEM0 TO PAUL S. CHECK 1

FROM ROY H. WOODS SUBJECT FORTHC0filNG MEETING WITH GE 85.80-118 8

7911060171 10/22/79 fiEMO TO COMMISSIONER 2

KENNEDY FROM HAROLD R. DENTON

SUBJECT:

INDEPENDENT CHECKS' 0F VALVE ALIGNMENT IN SAFETY-RELATED SYSTEMS

.86.80-118 9

8/15/77 MEMO TO T.H. NOVAK 14 FROM P'.S. CHECK

SUBJECT:

REACT 0P.

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FUELS INPUT TO ATWS REPORT

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87.80-118 10 7908020472 7/3/79 LETTER TO JAMES P. O'REILL'Y

'3 FM L.fi.- filLLS

SUBJECT:

SEQUOYAH NUCLEAR PLANTS 1 & 2 ERCW VALVE POSITIONING - NCR MEB 79-22 88.[80-118 11

'7908230193 7/24/79 MEM0 TO D. CRUTCHFIELD FM 4

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G. LAINES SUBJECT

89.80-118 12 7908130499 AUDIT PLAN 77-03 8

Mtl PUJAoUU+J FOIA-80-8

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F01A-00-47 F0IA-80-13e, APPENDIX A ~

F0IA-80-159 F01A-80-185 F01A-80~118 flRC FOIA NUMBER DOHERTY LIST NUMBER NRC ACCESSION NUMBER DOCUMENT DATE TYPE OF DOCUMENT PAGES 90,80-118 13 7908140506 5/11/79 Letter to Hendrie fm J.J.

4 Pickle 91.80-118 14 7908170240 7/16/79 Memo to S.H. Hanauer 30 fm T.M. Su

Subject:

Summary of Meeting Held on April 4,1979 with Representatives of the

~

General Electric Co to Discuss SRV Methodology 92.80-118',.

15 7901290277 1/16/79 IE Circular 79-02 7

93.80-118 16 7908010256 3/79 Reactor Primary Coolant 5

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System Pipe Rupture Study Method Detection for Sensitizatiot in Stainless Steel 17 7908020239

.5/3/79 Monthly Progress Rpt 7

94.80-118 Contract No. AT(49-24)-0293 95.80-118 18 c7907260492

.Rpt 50-498/79-08; 50-499/79-08 4 Conducted-5/15-18-79 96.80-118 19 7906180003 5/9/79' To ACRS Members fm Peter 8

Subject:

Summary of Responses to IE Bulletin 79-08 m

1

F01A-80-8 FO I A-80-17 F01 A-80-134 APPENDIX A_

FOIA-80-159 F0IA-80-185 F01A-802118 flRC FOIA NUMBER DOHERTY 1.IST NUMBER NRC ACCESSION NUMBER DOCUMENT DATE TYPE OF DOCUMENT PAGES 97.80-118 20 7906270003 4/17/79

. Bush

Subject:

Review of Duane To Andy Bates fm S.H.

3 Arnold RPV Nozzle Safe End Replacement Weldment Information 7906180348 4/12/79 Memo to A. Schwencer et. al 9

98.80-118 21 fm R. Vollmer, B. Grimes

Subject:

Expansion of Scope o'f 00R Generic Issue B-23, " Degraded Grid Vditage

99.80-118 22 7906070348 3/79 Proposed Revision 3 to

'18 Reg Guide 1.4 100.80-118 23 7911190328 8/11/79

'ACRS-1645 91 101.80-118 24 7911050098 10/17/79 Ltr fm H.R. Denton 3

102.80-118 25 7908220135 10/16/79 IE Bulletin 79-13 17 7910250475 11/20/79 IE Bulletin 79-26 14 103.80-118 26 104.80-118 27 7911270081 11/2/79 Memo to Steve Scott fm 5

Steven Varga,

Subject:

Board Notification - Rupture Strain

& Flow Blockage BN-79-36 t

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RE7 FOIA-UU J F01A-80-0 F01 A-80-17 FOIA-80-134 APPENDIX A F0IA-80-159 FOIA-80-135 F01A-80-11C URC FOIA NUMBER DOHERTY LIST NUMBER NRC' ACCESSION NUMBER DOCUMENT DATE TYPE OF DOCUMENT PAGES

'~

105.80-118 28 7911270086 10/31/79 Memo to S. Varga Fm 3

R.P. Denise

Subject:

Board Notification Rupture Strain and Flow Blockage Models in PWR Loca Calculations 106 80-118 29 7911140115 9/17/79 Progress Rpt 15 21 Contract'# NRC-04-78-242 107.80-118 30 7911290441 10/79

" Power Cooling Mismatch

.61 Test Series Test PR-1 Experiment Operating Specification" 7911195220 11/6/79 Ltr to Thomas D. Keenan 9

108.- 80-118 31

~

Fm D.F. Ross

Subject:

Request for Additional Information Concerning'NED0-24708 109.80-118 32 7911270359 11/13/79 Ltr to Richard Denise Fm 7

G. Sherwood

Subject:

PCI Program Status

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g

ret F0lA-80a3 F01A-80-8

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F01 A-80-17 F01A-80-13*,

APPENDIX A F0IA-80-159 F01A-80-185 F0!A-80 'll8 URC F0IA NUMBER DOHERTY LIST NUMBER NRC ACCESSION NUMBER DOCUMENT DATE TYPE OF DOCUMENT PAGES 110.80-118 33 7911270392 11/16/79 Ltr to D.F. Ross fm 3

Thomas Kennan

Subject:

Revised NED0-24708 Small Break Operator Guidelines 111.80-118 34 7911300415

11/16/79 Ltr to D.G. Eisenhut Fm 13 R.H. Buchholz Sbbject

GE g g g op Stress'at 112.80-118 35 7911300443 Ltr to Larry Phillips fm 2

. Luis F. Rodriguez

Subject:

NED0-20566-1 e-i G

b

RE: F0!A-80-3 F01A-80-8 F01A-80-47

~FOIA-80-134 APPENDIX B (CONSOLIDATED LIST OF DOCUMENTS NOT YET LOCATED)

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NRC FOIA NUMBER DOHERTY LIST NUMBER NRC ACCESSION NUMBER DOCUMENT DATE TYPE OF DOCUMENT PAGES

1) 80-3 4

3/11/75 Letter

2) 80-3 6

7905140169 9

3) 80-3 9

7905230449 2

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4) 80-3 10 7905240353 6:

5) 80-3 14 7909200004 68

6) 80-3 15 7909270424 10

7) 80-3 17 7907090244 8

B),80-3 18 7907050350

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3 9)'80-3 26 7902010134 1

0) 80-8 1

7901090086 20 1)80-8 2

7901100032 7

2) 80 5 5/4-5/78 Transcript 3)80-8 10 7902010051 43-4)80-8 11

~7902010006 14 i) '80-47 12 4/9/75 Letter e-t y

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APPENDIX B Page 2 NRC FOIA NUMBER DOHERTY LIST NUMBER NRC ACCESSION NUMBER DOCUMENT DATE TYPE OF DOCUMENT PAGES

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7)80-134 '

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Loc m or 27, 1979 g

l Director FREEDOM OF INFORMATION Office of Administration ACT. REQUEST.

U. S. Uuclear Regulatory Commission Washington D. C. 20555

[O[h-80-j

Dear Sir or Madam:

/Lfd h /-d-[d Pursuant to the Freedom of Information Act, 5 U.S.C.

E 552, as amended, John F. Doherty, Party-Intervenor in the Construction License Preccedings for the Allens Creek Nuclear Generat'ing Station, Docket 466, and a private citizen request the following documents concerning several aspects of safety of nuclear power plants, including:

a. Fuel rod clad safety

b. Pressure suppression containment systems

c. Recirculation pump overspeed

d. Anticipated Transient Without Scram

e. Steel containment shells

f. Reliability of stand-by emergency Senerators

g. Emergency sump pump reliability

h. Adquacy of main steam line radiation monitors

1. Pressure suppr3ssion pool integrity

j. Inadequate rapid fuel failure detection

k. Vaporization rate during ECCS operation

1. Fission product release during various evcats or nccidents

m. Water level indicators

n. Waterhammer induced pipe cracks; I

which are part of twenty (20) contentions accepted by the Atomic Safety and Licensing Board for this proceeding.

Is a citizen full party-intervenor, I request a waiver of the copying fee for requested documents. I have participat ed in the proceedings since April, 1979.

During that time I have filed ten sets of Interrogatories and the same number of document requests to both the NRC Staff and the utility Applicant.

I have filed se.veral procedural motions and testified ten hours at the Special Pre-hearing co'nference in October, 1979 Mr. Steven Sohinki, Counsel for the Staff may verify these statements for you.

He may be re-ached at 492-7268.

Further, that I am not a recipient of funds to carry on such work. I have received less than 5500 to carry out research on the status of problems listed cbove.

I am a law student, not currently employed, and with little available time for that if I am to participate meaning-fully in these proceedings.

Therefore, the documents and other items requested below are to be used in preparation for a Commission proceeding, and I request waiver of the usual copying fee for their duplication.

G l

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2 J E F. DW dRTY' DECE::32 27, 1979 FOIA RE9"13T Ls'

~

USHRC neport PbL-2494,, undocketed, " Data Report for the U,RC/PHL Halden Assembly IF1 P-31",

C.R. Hann, et al, April, 1978 (number of pages unknown)

Docket 50-266 i (Point Beach Nuclear Plant I or I7)

Letter, S. Burnstein iWisconsin Electric) to B. Rusche (NRC) of 12/30/75, "LER 50-266/75-13, " Failed Fuel Assembly D-03" (nuober of pages unknown)

Letter from Harold Denton (Office of nuclear Reactor Regulation) to G. Sherwood (General Electric Corp.), expressing concerns regardin6 approach to ATWS as set forth in NUREG-0460, Date of letter: August 4, 1978.

(length of letter unknown)

Note this may be in Docket #STN-50-550, GESSAR-BOP,or undocketed)

Letter fror D. F. Ross (NRC to G. Sherwood (General Electric) of March d I, 1975, regarding fuel damage acceptability during ATWS (Tergth of letter unknown) (Note: this asy be in STN 50-550, (GESSAR "JP), or undocketed) 7906290175 Summary of ACRS Sub-committee on ECCS 790116 meet.ng in Washington D. C. re: Issues related to ECCS 79/( 3/07,(D0 pagos) Undocketed.

7905140169 Comments on water reactro safety program...understan-ding of fuel failure needed. J. Hendrie, author.

(9pages) Undocketed 7905140392 Fo"Tarding letter with report NEDE 21,983P " Submerged structures Model, Main Vent Air Discharges,"Sobon, Gen.

Electric (Undocketed, 5 pages) 7905220348 Discusses.Liebnitz rule simplification & high heat transfer in LOCA models. Demonstrates G. E. conservative in peak clad temp. Stroupe, Gen. Elec. Author, ( Undodseted,11 pages)~

7905230449 Discusses rev. of ATWS suppl HUREG-0460, and that risk estimates cannot be improveds Buhl, A. R. URC. (Undocketed 2 pages) 7905240353 "BWR blowdoin/ ECC Program, Monthly Progress Rept.

for Mar. 1975."

Burnette, G. W. of Gen. Elec. (Undocketed, 6pages) 7905240990 Request additional info to complete reveiw of UEDE 21,821 "BWR Feedwater Hozzle/ Sparger" Eisenhut (NRC)

(Undocketed, 2 pages) r.7904050074, " Crack Arrest Methodology " Monthly Procress Rept Rosenfeld, BMI, auth.

(Undocketed, 2 pp)

O e

JOHN P. IniEit!Y'E M MBER 27, 1979 F.O.I. A.

UESTS

• '*703200385 Undocketed, 79/09/10, 3 pgs Inspection & Enforecement Circular " Proper Installation of Target Rock Safety-Relief Valves.

7909200004, Undocketed, 79/07/31, 68 pages " LOFT Monthly Progress Rept. June,, 1979 7909270424, Undocketed, 79/08/24, 10 pages, " Application of Internal Friction Hondestructive Evaluation Technique for Detecting Incipient Cracking of Bypass Lines & Pipesin BWRs.

7909270564 Undocketed, "BWR Blowdown / Emergency Core Cooling Program Monthly Progress Rept." (5 ptges).

7907690244 Undocketed, Discussion of imprecision in evaluatin)g buc.: ling criteriafor free-standing' containments. (8 pages 7907050350, Undocketed, Summary of ACRS meeting on ODYN code (2 pages 79/05/01 7907020465 Su n 'ary of ACRS meeting 79/01/31 with various utilities and vendors in Wa~shington D. C. re: ATWS for IWRS (38 pages) 7907200512, Undocketed, S. H. hanauer, TMI-2 Unresolved Safety Issues 79/07/06 Includes unresolved ACRS questions re BWRs.

(12 pages).

7907120686, undocketed, Office of Inspection and Enforcement 79/05/29; IE Info Notice 79-13 " Indication of Low Water Level in Oyster Creek Reactor. (9 pages).

9907060324, nondocketed, Results of comparisons of two-loop test apparatus and cladding temperature with models

( 4 pages) 7907250254,'nondocketed, Further clarification of information from two loop test apparatus 79/07/20 (3 pages) 7902140245, Docket 50-498, South Texas Pro.iect. In opposition to intrastate only operation. (2 pages)- -

7902120209, Docket 50-556, Black For. " Methodology to be'used re: Multiple Safety Relief, Valve Acutation." (3 pag 88) 7902010134, non-docketed; Rept. pres.e.nted to 6th water reactor safety research meeti,ng titled: " Pump Oversjeed Results" (1 page) l I

I appreciate your attention and effort in behalf of this request.

Please return this list if possible to me.

If there are any questions or other needs, Mr. Sobinki, may be able to assist you, as we are in frequent contact.

S'ncerely bd t.. John F. Doherty-4 o

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Januorv 3, 1979

)WI h2Mb Director Office of Administration FREEDOM OF INFORMATION U. S. Nuclear Regulatory Commission ACI REQUESI dashington D. C. 20555 f*0.TA to-P

Dear Sir or Madam:

g f p,g Pursuant to the Freedom of Information Act, 5 U.S.C.

E 552, as amended, John F. Doherty, Party-Intervenor in the Construction License Preccedings for the Allens Creek Nuclear Generating Station, Docket 466, and a private citizen request the following documents concerning several aspects of safety of nuclear power plants, including:

a. Fuel rod clad safety

b. Pressure supprossion containment systems

c. Recirculation pump overspeed

d. Anticipated Transient Uithout Scram

e. Steel containment shells

f. Reliability of stand-by emergency generators

g. Emergency sump pump reliability

h. Adquacy of main steam line radiation monitors

i. Pressure supprassion pool inte rity

j. Inadequate rapid fuel failure etection

k. Vaporization rate during ECCf

peration

1. Fission product release during various events or accidents

m. Water level indicators i,

p }ukb M M d/d d

n. Waterhammer induced pipe cracks; which are part of twenty (20) contentions accepted by the Atomic Safety and Licensing Board for this proceedin5

. is a citizen full party-intervenor, I request a waiver of the copying fee for requested documents. I have participat ed in the proceedings since April, 1979.

During that time I have filed ten sets of Interrogatories and the same number of document rcquests to both the NRC Staff and the utility Applicant.

I have filed several procedural motions and testified ten hours at the Specia'l Pre-hearing conference in October, 1979 Mr. Steven Sohinki, Counsel for the Staff may verify these statements for you.

He may be re-ached at 492-72Ga.

Further, that I am not a recipient of funds to carry on such work. I have received less than 5500 to c.arry out research on the status of problems listed Coove.

I am a law student, not currently employed, and with little available time for that if I am to participate meaning-fully.in these proceedings.

I Therefore, the documents and other items requested below are to be used in preparation for a Commission proceeding, and I request waiver of the usual copying fee for their duplication.

1 e

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. I!

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)

7901070385 Report b7 3 ::urfin on core maltdoun, L'.12 fuel rod behavior, e.tc. Undoemen -

(20 pa.es) a 7901100032 Summar" of 1:on destructive examination

leview croup meeting of 11/19/76. Uniocketed-(7 pages) 7901150005 Undocketed. Discusses state of fire protection Importance of ' flame retardant coating on cables.

(4 pages) 7901120227 Undocketed. Review of NED021,052 " Max Discharce of Liquid-Vapor Mixtures from Vessels. Eis hut (NRC) (12 pages)

Discussion of the amended application for the Allens Creek Nuclear Generatine Station, Unit 1 at the 217th ACRS meeting See Docket 50 h66, or ACRS files.

4 - 5,)1978.

held May (Length unknown Letter from G. G. Sherwood (General Electric) to H. C. Mosely (HRC) of Oct. 11, 1977in Docket STN 50-531, or STN 50-522. (Lenchh unknown)

Memo for M.D. Stolzenberg, (14RC) to Gary L.

Bennett (NRC, Office of IJuclear Reculatory Research) " Safety and Relief Valve Operation". Undocketed,(length unknown) i 7902230062 Donket STN 50-447, GESSAR-238, Forwarding letter for Gen. Electric docuement: " Interim Rrect. on Containment Loads for Mark III Containment" Undocketed (2 pages) 7901290330 Summary of 790012 meeting held with consultants and LWR fuel vendors re progress on fuel dama6e technical assistance, (26 pages) 7902010051 Undocketed. Report at 6th water safety research Mg.

"Results of the rR2 Nuclear Tests on the Behavior of Zircaloy Clad Fuel Rods." (43 pages) 7902010006'. Und o c'm t ed. Peacrt et 6th waster safety research Mtg.

" Inner Surface Oxidation "of Zircaloy Cladding in a LOCA (14 pages)

I appreciate Your attention and effort in behalf of this recuest.

Please return this list if possible to me.

If there are any nuestions or other needs, I'.r.

Schinki, may be able to assist vou, as we are in frequent contact.

Sine rel:/,

m/

hn F. Doherty 4327 Alconbury Lane #5 Houston, Texas 77021 S

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