ML17325A230

LER 87-013-00:on 870701 & 02,ice Buildup Discovered in Ice Condenser Flow Passages.Caused Possibly by Sublimation of Ice or High Humidity in Containment Air.Condenser Defrosted & Matter Discussed W/Utils That Have Same unit.W/870729 Ltr

ML17325A230
Person / Time
Site:	Cook
Issue date:	07/29/1987
From:	Postlewait T, Will Smith INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
LER-87-013, LER-87-13, NUDOCS 8708040031
Download: ML17325A230 (15)

Text

REGULA Y INFORMATION DISTRIBUTIOI" YSTEM <RIDS),

ACCESSION NBR: 8708040031 DOC. DATE: '87/07/29 NOTARIZED: NO DOCKET FACIL: 50-315 Donald C. Cook Nuclear Power Planti Unit ii Indian~

Indiana iDc 05000315 AUTH. NAME AUTHOR AFFILIATION POSTLEWAITEI T. -Indiana 5 Michigan Electric Co.

SMETHE W. G. Indiana 5 Michigan Electric Co.

RECIP. NAME RECIPIENT AFFILIATION

SUBJECT:

LER 87-013-00: on 870701 cc 02 discovered ice buildup in ice condenser in ice condenser flow passages. Caused possibly bg sublimation of ice or high humiditg in containment air. Ice condenser d e frosted. W/870729 ltr.

DISTRIBUTION CODE:. IE22D COPIES RECEIVED: LTR I ENCL BIIE:

TITLE: 50. 73 Licensee Event Report (LER)I Incident Rpti etc.

NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-3 LA 1 1 PD3-3 PD 1 WIGGINGTON D 1 INTERNAL: ACRS MICHELSON 1 ACRS MOELLER 2 2 AEOD/DOA 1 f AEOD/DBP/NAS 1 1 AEOD/DSP/ROAB 2 2 AEOD/DSP/TPAB 1 1 DEDRO f NRR/DEBT/ADE 1 0 NRR/DEBT/ADS 1 0 NRR/DEBT/CEB 1 NRR/DEST/ELB 1 1 NRR/DEBT/ ICSB 1 1 NRR/DEST/MEB f NRR/DEBT/MTB NRR/DEST/PSB 1 NRR/DEST/RBB 1 1 NRR/DEBT/SGB 1 NRR/DLPG/HFB NRR/DLPG/GAB 1 NRR/DOE*/EAB 1 1 NRR/DREP/RAB 1 1 NRR/DREP/RPB 2 2 NgR/PMAS4,1LRB 1 NRR/PMAB/PTSB 1 1

~RRC PI.LBr 02 1 1 RES DEPY GI 1 RES TELFORDi J 1 1 RES/DE/EIB 1 1 RQN3 FILE 01 1 f EXTERNAL: EQ8cQ QROH> M 5 5 H ST LOBBY WARD LPDR 1 NRC PDR 1 NSIC HARB ISI J i 1 NBIC MAYSi Q 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 45 ENCL 43

QRC Form 355 US. NUCLEAR RfOULATORY COSN4ISSION (94)3) APPROVED OMS NO. 3(100104 EXPIRES: SI31 IN LICENSEE EVENT REPORT (LER)

PA FACILITYNAME ul DOCKET NUMSER (2)

D. C. Cook Nuclear Plant - Unit 1 0 5 00 031510F13 TITLE (4)

ICE BUILDUP IN ICE CONDENSER PLOW PASSAGES DUE TO SUBLIMATION EVENT DATE 15) LER NUMBER (5) REPORT DATE (7) OTHER FACILITIES INVOLVED (N Sf QUSNVIAL RSV~SR MONTH DAY FACILITYNAMES DOCKET NVMSER(S)

MONTH OAY YfAR YEAR NUMSER AS YEAR 0 5 0 0 0 0 7 0 1 8 7 8 7 0 1 3 0 00 72 98 7 0 5 0 0 0 THIS REPORT IS SUSMITTEO PURSUANT 7 0 THE Rf OUIREMENTS OF 10 CF R (): IChrch onr or more ol the lollowinP) (11 OPERATINQ MODE (8) 5 20.402 (Sl 20A05(c) 50.73(o) (2) llrl 73.71(d) 20.405( ~ )(I)II) 50.35(c) (I) 50.73(o) (2)(rl 73.71(c)

POWER LEVEL OTHER ISpecliy in Adrtrrct p p p 20A05(o) II) (ill 50.38(c)(2) 50.73(o) l2)(vQ) dHow rnd In Trxt, HIIC Fohn 20AN(o l(1) (IQ) 50.73(e) (2) (I) 50.73(o) (2)(rill)IA) 3SSA) 20A08leHI)(lv) 50.73(el(2)(S) 50,73( ~ l(2)(vill)(8) 20.405( ~ IIII(v) 50.73lel(2) IIII) 50.73(el l2) (el LICENSEE CONTACT FOR THIS LER (12)

NAME ~ TELEPHONE NUMBER T. K. Postlewait- AREA CODE Technical Engineering Superintendent 6 1 6 4 6 5 - 5 9 0 1 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRISED IN THIS REPORT (13) c MANVFAC EPORTASLE MANUFAC. EPORTASLE I c UsE 5Y$ TE COMPONf NT CAUSE SYSTEM COMPONENT TURER TO NPROS jjrIISSQIIax TVRER MONTH OAY YEAR SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED SV 8 M I SS ION DATE (15)

YES Illyrr, complete EXPECTED SVShtlSSIOH DATE/ NO AssTRAcT ILimit to tr00 rprcrr, I r., rpproximrtely liltren rtnprrepecr typewritten linml (15)

Between July 1 and 2, 1987, with Unit 1 in Mode 5 (Cold Shutdown), flow passage inspections of the ice condenser revealed frost and ice buildup on the lattice frames of greater than 3/8 inch in a total of one hundred twenty-four flow passages in seven of the twenty-four ice condenser bays.

A subsequent inspection indicated that there was also frost and ice formation between the walls and ice baskets adjacent to the walls.

Technical Specification (T/S) 4.6.5.1.b.3 limits frost or ice buildup in flow passages to a nominal thickness of 3/8 inch. According to this T/S, buildup exceeding this limit in two or more flow passages per bay is evidence of abnormal degradation. Though our evaluation has concluded that the degradation is not serious, we believe issuance of this voluntary LER is appropriate since some degradation has been identified.

Actions taken to correct the abnormal degradation included a defrost of the ice condenser and an internal investigation of the event. The internal investigation, aided by a previous Westinghouse evaluation, indicated that there were no safety concerns, that is, that the ice condenser remained in a configuration in which it would have performed its intended safety function.

870804003i 870729 PDR ADOCK 050003i 5 8 PDR ~ w NRC Form 385 (903)

NRC Form 388A ~ V.S. NUCLEAR REOVLATORY COMMISSION

$ 83)

LICENSEE E NT REPORT tLER) TEXT CONTINUAT APPROVEO OMS NO. 3160&lpl EXPIRES: 8/31/88 FACILITYNAME 11) DOCKET NUMBER Ql LER NUMBER (8) PACE 131 SEQUENTIAL )5j< REVISION D. C. Cook Nuclear Plant- YEAR NUMSER <4 NUMSER Unit

/3'/INES <<Moo JI IEI)uhd, 1

ow edcNonel A//IC %%dnh 38SA3/ l)7) 06000315 8 7 0 1 3870'2 OF 1 3 Conditions Prior to Occurrence Unit 1 in Mode 5,(Cold Shutdown)

Descri tion of Event The as-found visual inspection ice condenser (EIIS/COND) flow passages conducted on July 1 and 2, 1987, indicated frost and ice accumulation greater than 3/8 inch in two flow passages in Bay 1, four flow passages in Bay 4,,two flow passages in Bay 13, two flow passages in Bay 18, two flow passages in Bay 19, four flow passages in Bay 22 and four flow passages in Bay 24. Subsequently, the inspection was expanded to include at least twenty additional flow passages in each bay. This inspection revealed an additional twelve flow passages in Bay 1, twenty-two flow passages in Bay 4, six flow passages in Bay 13, four flow passages in Bay 18, twenty-four flow passages in Bay 18, twenty-four flow passages in Bay 19, twenty-four flow passages in Bay 22, and twelve flow passages in Bay 24 with more than 3/8 inch frost and ice buildup for a total of 124 flow passages. There are a total of 3072 flow passages in the Ice Condenser.

Attachments 1 through 9 graphically describe the geometry of the flow passages and the location of the ice/frost accumulation.

Technical Specification (T/S) 4.6.5.1.b.3 requires that the ice condenser be determined operable at least once per 9 months by verifying, via visual inspection of at least two flow passages per ice condenser bay, that accumulation of frost or ice on flow passages between ice baskets (EIIS/BSKT),

past lattice frames (EIIS/FRM), through the intermediate and top deck floor grating, or past the lower inlet plenums support structures (EIIS/SPT) and turning vanes is restricted to a nominal thickness of 3/8 inch. If one flow passage per bay is found to have an accumulation of frost or ice greater than this thickness, a representative sample of twenty additional flow passages from the same bay shall be visually inspected. If these additional flow passages are found acceptable, the surveillance program may proceed considering the single deficiency as unique and acceptable. More than one restricted flow passage per bay is evidence of abnormal degradation of the ice condenser.

A subsequent partial inspection also revealed ice formation in the area between the containment wall and the Row 1 baskets. It is believed that there is additional ice formation in the area between the crane wall and Row 9 Ice

'on'denser baskets. This is similar to that identified during the most recent Unit 2-Surveillance (see LER 50-316/87-002). The ice, which in general is not, visible from the upper or lower plenum areas of the ice condenser, has led to certain difficulties, which has made it more difficult to free the required number of wall baskets for weighing. However, our NSSS vendor, Westinghouse, has indicated (from the evaluation for the condition identified during the Unit 2 occurrence) that such ice is not unexpected and is not of significance with respect to public health and safety.

NRC~ 3SSA o V 8 OPO IP8~2l S38/ISS EAO)

NRC Form 386A U rL NUCLEAR REOULATORY COMMISSION

)663)

LICENSEE E NT REPORT (LER) TEXT CONTINUA'1 APPROVED OMS NO. 3160-0)04 EXPIRES: 8/31/66 FACILITYNAME ill DOCKET NUMSER (2) LER NUMBER )6) PACE )3)

~% SEQUENTIAL REVISION D. C. Cook Nuclear Plant- YEAR NVMSER NVMSS R Unit 1 5 0 0 0 3 1 5 8 7 0 1 3 0 0 0 3 OF 1

%mls Nmco /r rsfv)INE ces s/&/cns//INC Farm 3/)/)AS/ <IT)

Descri tion of Event (cont'd)

During the surveillance interval prior to the July 1, 1987, test, several of

'he 60 air handling units (AHU) (EIIS/AHU) (used to maintain ice condenser temperature) were intermittently inoperable for maintenance and/or repair.

However, it ha's'been concluded that the inoperability of the AHU's did not significantly contribute to the frost and ice formation experienced.

With the exception of the AHUTs, there were no inoperable structures, components or systems that contributed to this event.

Cause of Event It is believed that sublimation of ice or high humidity in the containment air could have contributed to this problem. Further investigation of this event is ongoing.

Anal sis of Event The Westinghou'se evaluation indicated that lattice frost/ice formation of up to 20 percent of the total flow passage area could be present without the peak Containment Pressure exceeding the design limit. Since the frost/ice buildup identified in Bays I, 4, 13, 18, 19, 22 and 24 constitutes a total flow blockage area which is less than the 20 percent limit, this situation is bounded by the Westinghouse evaluation.

Our evaluation indicates that the amount of flow blockage due to frost and ice buildup noted in the Ice Condenser can be tolerated without adversely affecting the Ice Condenser function during a Loss of Coolant Accident.

Based on the above information and the Westinghouse evaluation, it is concluded that the abnormal degradation event does not constitute an unreviewed safety question as defined in 10CFR50.59(a)(2), nor does it adversely impact health and safety.

Though our evaluation has concluded that the degradation is not serious, we believe issuance of this voluntary LER is appropriate since some degradation has been identified.

i 'NRC'FORM SSSA .o U.S.QPO:1066.0424 636/466 N 643)

NRC FoTm 354A US. NUCLEAR REOULATORY COMMISSION (983)

'CENSEE E NT REPORT (LER) TEXT CONTINUAT N APPROVEO OMS NO. 3(9)&)04 EXPIRES: 8/31/88 FACILITYNAME l) I OOCKET NUMBER (2) LER NUMBER (8) PAOE (3)

SEQUENTIAL D. C. Cook Nuclear Plant- YEAR NUMBER 'PS RE V IS ION NUMBER Unit 1 OF 5 8 7 0 3 TEXT //mom N>>BB EI /BqUEe4 I>>B /EE/o/>>///RC hvm BSSAS/ l)7)

Corrective Actions The corrective action was to defrost the ice condens'er, including manual scraping of the ice, to remove the accessible frost and ice buildup.

We are discussing this situation with other utilities who have ice condenser units. The discussions center around common problems with ice condenser units and common solutions to these problems.

Failed Com onent Identification II No component failures were identified during this event.

Previous Similar Events LER 50-316/85-013 LER 50-316/86-002 WRC'A)AMSBBA o U.S.GPO:1988~24 538/455 (9E)3)

NRC Form 3SSA U5. NUCLEAR REGULATORY COMMISSION

($ 83)

LICENSEE EYENT REPORT (LER) TEXT CONTINUATI APPROVED OMB NO. 3150-0)04 EXPIRES: B/31/BS FACILITYNAME (ll DOCKET NUMBER (2) LER NUMBER (S) PAGE (31 SEQUENTIAL REVISION D. C. Cook Nuclear Plant- YEAR NUM SJI NUMOSA Unit 1 o s o o o3 158 7 0 1 3 0 0 0 5 OF 1 3 TEXT ///mao <<Mco 4/oqoborS Iroo akNono/HRC Forrrr 3//SAS) (17)

ATTACHMENT 1 Description of Flow Passage Blockage by Category (affected Flow Passages are indicated by the boxed areas on the following attachments).

~Cate ot A Maximum Flow Passage Ice/Frost Blockage greater than 75 percent.

Maximum Flow Passage Ice/Frost Blockage between 50 and 75 percent.

Maximum Flow Passage Ice/Frost Blockage between 25 and 50 percent.

Maximum Flow Passage Ice/Frost Blockage less than 25 percent (but greater than 3/8" build-up).

• NOTE: These are generalized categories which reflect the maximum ice/frost blockage found in a particular flow passage and in general was limited to one or two lattice frameworks in the flow passage. This does not indicate that the flow passage was blocked it's entire length. Lattice Framework is located at the positions of cruciforms in the ice basket. Cruciforms are installed every six feet within the 48, foot ice basket (for convention the "top" lattice framework is referred to as number 1, etc.) The specific lattice frameworks affected are indicated on the individual Bay drawings (Attachments 3

- 9).

'o/lIC Pd/IM SSBA *U,S,GPO:1060D421438l46S RPB31

NRC Form 3SEA'883)

U.S. NUCLEAR REGULATORy COMMISSION LICENSEE EVENT REPORT (LER) TEXT CONTINUA N APPROVED OM8 NO, 3150M(04 EXP( RES I 8/31/88 FACIL)TYNAME ('I) DOCKET NUMSER (2) LER NUMSER (5) PAGE (3)

VE*R $~ SEOUENTIAL NUMBER QgG REVISION

'?A NUMBER D. C. Cook Nuclear Plant - Unit 1 0 0 o s o o o 3 8 7 1 3 0 0 60F I 3 TEXT /EIIKBB<<Moo 4I /BEB4aE Boo /Er/Boo/PVRC Forrrr 3////43/(1 7)

ATTACHMENT 2 Representative Diagram of Two Flow Passages Lattice Framework Technical Specification nominal thickness (3/8 inch)

Scale:

1/2 inch equals 1 inch

'N)IC FORM.SBBA *U.S.GPO:(08tH)4)24 u8/455 rowel

NRC Form SBBA US. NUCLEAR REOULATORY COMMISSION (983)

LICENSEE EVENT REPORT ILER) TEXT CONTINUAT APPROVED OMB NO. SI SOLI(M EXPIRES: 8/81/88 FACILITY NAME (1) DOCKET NUMBER (S) LER NUMBER (6) PACE (3)

YEAR SSIr. SEQUENTIAL NUMBER REVISION NUMBER D. C. Cook Nuclear Plant - Unit 1 0 6 0 0 0 3 ] 5 8 70 1 3 0 0 0 7 OF 1 TEXT /8'mao <<Moo <</BBISIR/. uoo ss(I/one/ HRC hvm SSSA8/ (1Tl ATTACHMENT 3 Bay 1 (of 24 total)

Azimuthal Row (Basket)

D(1) A(3) D(2) A(2) 4" 5 c(z)

Radial Row (Row)

NOTE: The Lattice Prameworks -affected are indicated in parenthesis after the category description number (see Attachment 1).

'WRC FORM SSBA ~U S QPO (888-0()84-888/686 ~

CAN)

NRC PoNR 3SSA US. NUCLEAR REOULATORY COMMISSION (093)

LICENSEE EVENT REPORT (LER) TEXT CONTINUATI APPROVED OMS NOi 3(SOW(04 EXPIRES: 8/31/SS PACIUTY NAME (1) DOCKET NUMBER (2) LER NUMBER (S) PACE (3)

YEAR ERE SEQUENTIAL REVISION NUM ER NUMSER D. C. Cook Nuclear Plant - Unit 1 0 S 0 0 0 3 ] 5 8 7 0 1 3 0 0 0 SOF1 3 TEXT fE/RS/S ERECT /E nyuhd, UES S///ERE/NRC %%de 3SSES/03)

ATTACHMENT 4 Bay 4 (of 24 total)

Azimuthal Row (Basket)

A(2) B( ) A( )

4 5 6 C(7) C(7)

Radial Row (Row)

D(2) -

D(2 and 3) D(2)

NOTRE The Lattice Frameworks affected are indicated in parengthesis after the category description number (see Attachment 1).

NhC'PORM Say, *U.S.GPO:(985 0-02E 538/SSS (9()3)

NRC Form 36SA US. NUCLEAR REOULATORY COMMISSION (SS3)

LICENSEE E NT REPORT (LER) TEXT CONTINUA N APPROVEO OMS NO. 3160M)OS EXPIRES: 6/31/SS FACILITYNAME l1) DOCKET NUMBER (3) LER NUMBER (6) PACE (3)

YEAR SEQUENTIAL 'AR REVISION NUMBER NUMSER D. C. Cook Nuclear Plant - Unit 1 0 0 0 3.1 58 70 1 30 0 0 9 OF 1 3 TlXT/NRXVS g>>CS /S /SESS', INS SIENOnel ///IC %%dnn 3//EAS/ l 17)

ATTACHMENT 5 Bay 13 (of 24 total)

Azimuthal Row (Basket)

B(2) D(2) C(2) 3 Radial Row (Row)

NOTE: The Lattice Frameworks affected are indicated in parenthesis after the category description number (see Attachment 1).

INIC PORMiSSSA *U.S.QPO:196~634 63SAC66 '~

"'(ES3)

NRC Form 368A U.S. NUCLEAR REGULATORY COMMISSION

)943)

UGENSEE E T REPORT (LER) TEXT CONTINUAT APPROVED OMS NO. 3)50-0)04 EXPIRES: 8/31/8S FACILITYNAME I I I DOCKET NUMSER I2) LER NUMBER )5) PAGE I3)

YEAR gr'j

...i?

SEGUSNTIAL NUMBER REvrsloN NUMSSR D. C. Cook Nuclear Plant - Unit 1 3 1 5 8 7 0 1 3 0 0 1 0 TEXT /8'Irxss Nrsos /I rsSSSsrL Uoo SEr/oo>>////IC Form SSSAS/ l 1 7)

ATTACHMENT 6 Bay 18 (of 24 total)

Azimuthal Row -(Basket)

Radial Row (Row) 7 D(2)

NOTE: The Lattice Frameworks affected are indicated in parenthesis after the category description number (see Attachment 1).

NRC FORM SSSA *U.S.GPO:1086-0-624 638/455 IQ$3)

NRC Form SSSA US. NUCLEAR REOULATORY COMMISSION (983)

LICENSEE E T REPORT (LER1 TEXT CONTINUAT APPROVED OMS NO. 3150-0)04 EXPIRES: 8/31/88 FACILITYNAME (1) DOCKET NUMBER (2) LER NUMBER IS) PACE (3)

SEOVENTIAL 'EVISION YEAR ox NUMBER 4% NVMBER D. C. Cook Nuclear Plant - Unit 1 o s o o o 3 1 5 8 7 0 13. 0 0 1 10F 1 3

//mac <<ece /s /sqv)BIL vsB ESI/sns//YRC hem ~S/ (IT)

ATTACHMENT 7 Bay 19 (of 24 total)

Azimuthal Row (Basket)

D(2 and 7) C(2 and 7) D(2) D(3) C(2 and 7) B(2) 3 4 5 6 7 8" -

9 D(2)

C(2)

D(2 and 3 A(2)

Radial Row (Row)

NOTE: The Lattice Frameworks affected are indicated in parenthesis after the category description number (see Attachment 1).

I hC'FO I)M SSBA *U.S.GPO:1888&24 538/455 8)EQ)

NRC Form 366A UA. NUCLEAR REOULATORY COMMISSION 1883) ~

LICENSEE E T REPORT (LER) TEXT CONTINUA APPROVED OMB NO. 319)&184 EXPIRES: 8/31/88 FACILITYNAME 11) DOCKET NUMBER l2) LER NUMBER 16) PACE 13) yEAR >~j SEOUENTIAL NUMSER REVISION NUM ER D. C. Cook Nuclear Plant Unit 1 o 5 o o o 3158 7 0 13 0 0 1 2 1 3 TEXT /4I mme ~ /E /sqESsd, Use aRWone/Nl)C AmI 36648/ 117)

ATTACHMENT 6 Bay 22 (of 24 total)

Azimuthal =Row (Basket)

Radial Row (Row)

D(2)

D(2) B(2) A(2) B(2) C(2)

A(2)

NOTE: The Lattice Frameworks affected are indicated= in parenthesis after the category description number (see Attachment 1).

m U.S.GPO:1 966O4)24 538/4SS C FORM 346A

'f043)

NRC Form 388A U.S. NUCLEAR REGULATORY COMMISSION IS83)a LICENSEE EV T REPORT (LER) TEXT CONTINUAT APPROVEO OMS NO. 3160M)OS EXPIRES: 8/31/88 FACILITYNAME 11) OOCKET NUMBER 12) LER NUMBER (6) PAGE 13)

YEAR ~ SECIUENTIAL NUMBER

~ REVISION

>AN NUMSER D. C. Cook Nuclear'lant - Unit 1 0 0 30F1 0 5 0 0 0 3 ] 5 8 7 1 3 0 1 3 TERT /3'IINBS ~eCe EI nqatBd, INB akRSVN/ Y/IC %%drm AM3/ {)7)

ATTACHMENT 9 Bay 24 (of 24 total)

Azimuthal Row (Bask'et)

A(2 and 7) A(7) C(2 and 7) D(2 and 7)

B(2).

Radial Row (Row)

C(2)

NOTE: The Lattice Frameworks affected are indicated in parenthesis after the category description number (see Attachment 1).

tIRC FORM SBSA *U.S.GPO:I SStHH24 538/E55 8)30)

h llOPlosA Ieotrlo yste t

INDIANA8t NICH/GAIJI ElECTRIC CONPA IVY DONALD C. COOK NUCLEAR PLANT P.O. Box 456, Brldeeman, Ml 49106 Telephone (616) 465.5901 July 29, 1987 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Operating License DPR-58 Docket No. 50-315 Document Control Manager:

In accordance with the criteria established by 10 CFR 50.73 entitled Licensee Event Re ortin S stem, the following report is being submitted:

87-013-00 Sincerely, W. G. Smith, r.

Plant Manager

/afh Attachment cc: John E. Dolan A. B. Davis, Region M. P. Alexich III R. F. Kroeger H. B. Brugger R. W. Jurgensen NRC Resident Inspector R. C. Callen G. Charnoff, Esp.

D. Hahn INPO D. Wigginton, NRC PNSRC A. A. Blind Dottie Sherman, ANI Library J. G. Feinstein/B. P. Lauzau File