ML17263A818

LER 94-012-00:on 940921,approx 1032 Edst W/Reactor at Approx 98% Steady State Power,Power from Circuit 751 Was Lost. Caused by Automatic Actuation of B Emergency D/G Was Due to Undervoltage.Safeguards Buses Were restored.W/941021 Ltr

ML17263A818
Person / Time
Site:	Ginna
Issue date:	10/21/1994
From:	Martin J, Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-94-012, LER-94-12, NUDOCS 9410310306
Download: ML17263A818 (11)

Text

'

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR: 94 103 10306 DOC. DATE: 94/10/2 1 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION MARTIN,J.T. Rochester Gas & Electric, Corp.

MECREDY,R.C. Rochester Gas & Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R. Document Control Branch (Document Control Desk)

SUBJECT:

LER 94-012-00:on 940921,approx 1032 EDST w/reactor at approx 984 steady state power, power from circuit 751 was lost.

Caused by automatic actuation of "B" emergency D/G was due to undervoltage.Safeguards buses were restored.W/941021 ltr.

DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL SIZE:

TITLE: 50.73/50.9 Licensee Event Report (LER), ncident Rpt, etc.

NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-3 PD 1 1 JOHNSON,A 1 1 INTERNAL~AEOD/ROAB/DSP 2 2 AEOD/SPD/RRAB 1 1

~LR CENTE~R NRR/DE/EMEB 02 1 1 NRR/DE/EELB 1 1 1 1 NRR/DORS/OEAB 1 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOLB 1 1 NRR/DRSS/PRPB 2 2 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NRR/PMAS/IRCB-E 1 1 RES/DSIR/EIB 1 RGN1 FILE 01 1 1 EXTERNAL: L ST LOBBY WARD 1 1 LITCO BRYCE,J H 2 2 NOAC MURPHY i G ~ A 1 1 NOAC POORE,W. 1 1 NRC PDR 1 1 NUDOCS FULL TXT 1 1 XO'I'E TO Al.l. "RIDS" RFCIPI Ei I':

PLE.KSE IIEI.P I'S TO RFDI.'CE SVELTE'CONTE( 1"I'I IF. DOCl'iII:.i I'COiTROI.

DESk. ROOiI PI.3, (FX I; 304.'083 ) 'I'0 I:LIXIIMI'E. 5'()i'l4 %ALII'. I:lIOil DIS'I'RID L"I'ION I.IS'I'S I'OR DOCI 'iII'.N'I'S 5 () I IX)i"I' I I'.I>'ULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 26 ENCL 26

,'nc coen ss*TC ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 EAST AVENUE, ROCHESTER N. Y. 14649-0001 ROBERT@ MECREDY TEEEPHONE Vice fsesident AREA GOOE 716 546 2700 Cinne Nueieei Psodussion October 21, 1994 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Allen R. Johnson PWR Project Directorate I-3 Washington, D.C. 20555

Subject:

LER 94-012, Loss of 34.5 KV Offsite Power Circuit 751, Due to External Cause, Results in Automatic Start of "B" Emergency Diesel Generator R.E. Ginna Nuclear Power Plant Docket No. 50-244 In accordance with 10 CFR 50.73, Licensee Event Report System, item (a) (2) (iv), which requires a report of, "any event or condition that resulted in a manual or automatic actuation of any engineered safety feature (ESF), including the reactor protection system (RPS)", the attached Licensee Event Report LER 94-012 is hereby submitted.

This event has in no way affected the public's health and safety.

Very uly yours, Robert C. Mecredy xc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna USNRC Senior Resident Inspector 9410310306 941021 PDR ADQCK 05000244 gpss S PDR

~ ~

NRC FORH.366, U.S. NUCLEAR REGULATORY COHMISSION APPROVED BY OHB NO. 3150 ~ 0104 (5.92) EXPIRES 5/31/95 ESTIHATED BURDEN PER RESPONSE TO COHPLY WITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS.

LICENSEE EVENT REPORT (LER) FORWARD COHHEHTS REGARDIHG BURDEN ESTIMATE TO THE INFORMATION AND RECORDS HANAGEMENT BRANCH (HHBB 7714), U.ST NUCLEAR REGULATORY COMMISSION/

(See reverse for required number of digits/characters for each block) WASHIHGTOH, DC 20555-0001, AHD TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AHD BUDGET 'WASHINGTON DC 20503.

FAGILITY NAHE (1) R.E. Ginna Nuclear Power Plant DOCKET NUHBER (2) PAGE (3) 05000244 '1 OF 8 TITLE (4) Loss of 34.5 KV Offsite Po~er Circuit 751, Due to External Cause, Results in Automatic Start of iiga Emergency Diesel Generator EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (B)

SEQUENTIAL REVISION FACILITY NAME DOCKET NUHBER MONTH DAY YEAR YEAR MONTH DAY YEAR NUHBER HUHBER 09 21 94 94 --012-- 00 10 21 FACILITY NAHE DOCKET NUMBER OPERATING N

THIS REPORT IS SUBHITTED PURSUANT TO THE RE UIREMENTS OF 10 CFR 5: (Check one or more) (ll)

HODE (9) 20.402(b) 20.405(c) 50.73(a)(2)(iv) 73.71(b)

POMER 20.405(a )(1)(i) 50.36(c)('1) 50.73(a)(2)(v) 73.71(c) 098 LEVEL (10) 20.405(a)(1)(ii) 50.36(c)(2) 50.73(a)(2)(vii) OTHER 20.405(a)(1)(iii) 50.73(a)(2)(i) 50.73(a)(2)(viii)(A) (Specify in 20.405(a)(1)(iv) 50 '3(a)(2)(ii) 50.73(a)(2)(viii)(B) Abstract and in Text, below 20.405(a)(1)(v) 50.73(a)(2)(ill) 50.73(a)(2)(x) HRC Form 366A)

LICENSEE CONTACT FOR THIS LER (12)

HAHE John T. St ~ Hartin - Director, Operating Experience TELEPHONE HUHBER (Include Area Code)

(315) 524-4446 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

REPORTABLE REPORTABLE CAUSE SYSTEH COHPONENT MANUFACTURER CAUSE SYSTEM COHPOHEHT MANUFACTURER TO NPRDS TO NPRDS EA CBL5 XOOO N SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED HOHTH DAY YEAR YES SUB HISS ION (If yes, complete EXPECTED SUBMISSION DATE) ~

X NO DATE (15)

ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16)

On September 21, 1994, at approximately 1032 EDST, with the reactor at approximately 98~ steady state power, power from Circuit 751 (34.5 KV offsite power source) was lost. This resulted in deenergization of 4160 Volt bus 12B, and momentary loss of power to "B" train 480 Volt safeguards buses 16 and 17.

The "B" Emergency Diesel Generator started and reenergized buses 16 and 17, as per design.

The underlying cause of the loss of power from Circuit 751 was that a tree was accidently knocked into the transmission wires for Circuit 751 by a private citizen operating heavy equipment. This event is NUREG-1022 Cause Code (C) .

Corrective action to preclude repetition is outlined in Section V.B.

NRC FORH 366 (5-92)

HRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVEO BY OHB HO. ~ 3150-0104 (5-92) EXPIRES 5/31/95 I

ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS IHFORMATION COLLECTION REQUEST: 50.0 HRS.

FOR'WARD COMMENTS REGARDING BURDEN ESTIMATE TO LICENSEE EVENT REPORT (LER) THE INFORMATION AND RECORDS MANAGEHENT BRANCH TEXT CONTINUATION (MNBB 7714), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555-0001 AHD TO THE PAPERWORK REDUCTION PROJECT (3110-0104), OFFICE OF MANAGEMEHT AND BUDGET WASHINGTON DC 20503.

FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)

YEAR SEQUEHTIAL REVISION R.E. Ginna Nuclear Power Plant 05000244 2 OF 8 94 012 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)

PRE-EVENT PLANT CONDITIONS The plant was at approximately 98'teady state reactor power with no major operational activities in progress'he offsite power configuration to the plant was in the normal n50%

/50%" offsite power lineup:

o Circuit 751 (34.5 KV offsite power source) was supplying power to the "B" train safeguards buses 16 and 17 through 34.5 KV to 4160 Volt transformer 12A (12A transformer) to 4160 Volt bus 12B, and through the safeguards bus 4160 Volt to 480 Volt transformers.

o Circuit 767 (34.5 KV offsite power source) was supplying power to the "A" train safeguards buses 14 and 18 through 34.5 KV to 4160 Volt transformer 12B (12B transformer) to 4160 Volt bus 12A, and through the safeguards bus 4160 Volt to 480 Volt transformers.

See the attached sketch of the offsite power distribution system.

II. DESCRIPTION OF EVENT A. DATES AND APPROXIMATE TIMES OF MAJOR OCCURRENCES:

o September 21, 1994, 1032 EDST: Event date and time.

o September 21, 1994, 1032 EDST: Discovery date and time.

o September 21, 1994, 1032 EDST: Control Room operators verify the "B" Emergency Diesel Generator (D/G) operation and safeguards buses 16 and 17 energized.

o September 21, 1994, 1102 EDST: Safeguards buses 16 and 17 were resupplied from Circuit 767.

o September 21, 1994, 1108 EDST: The "B" Emergency D/G was stopped and realigned for auto standby.

o September 21, 1994, 1239 EDST: Circuit 751 declared operable.

NRC FORM 366A (5-92)

NRC FORM 366A U.S. NUCLEAR REGULATORY COHHISSION APPROVED BY OHB NO. 3150.0104 (5-92) EXP I RES 5/31/95 ESTIHATED BURDEN PER RESPONSE TO COMPLY IIITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS.

FORNARD COMMENTS REGARDING BURDEN ESTIHATE TO LICENSEE EVENT REPORT (LER) THE INFORHATION AND RECORDS HANAGEHENT BRANCH TEXT CONTINUATION (HNBB 7714), U.ST NUCLEAR REGULATORY COMMISSION, HASHINGTON, DC 20555-0001 AND TO THE PAPERNORK REDUCTION PROJECT (31/0-0104), OFFICE OF MANAGEMENT AND BUDGET WASHINGTON DC 20503.

FACILITY NAHE (1) DOCKET NUMBER (2) LER NUHBER (6) PAGE (3)

SEQUENTIAL REVISION R.E. Ginna Nuclear Power Plant 05000244 YEAR 94 00 3 OF 8 012 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)

B. EVENT:

1 On September 21, 1994, at approximately 1032 EDST, with the reactor at approximately 98: steady state full power, the Control Room received numerous annunciator alarms. The Control Room operators immediately determined that Circuit 751 (34.5 KV offsite power source) was deenergized, that "B" train safeguards buses 16 and 17 had lost their power supply from 4160 Volt bus 12B, and that the "B" Emergency D/G had started and was tied to safeguards buses 16 and 17.

The Control Room operators immediately performed the appropriate actions of Abnormal Procedure AP-ELEC.1 (Loss of 12A And/Or 12B Transformer) to stabilize the plant, and verified that the "B" Emergency D/G was operating properly and that safeguards buses 16 and 17 were energized. The Control Room operators observed Circuit 751 and bus 12B displayed zero (0) voltage. The lossthat of power from Circuit 751 resulted in undervoltage on safeguards buses 16 and 17, and the "B" Emergency D/G started and reenergized these buses, as per design.

Energy Operations personnel were notified concerning the loss of Circuit 751. Personnel from the "Engineering, Operations, and Gas Services" department investigated field conditions and determined that a private citizen (non-RG&E employee) had been operating heavy equipment near an overhead line for Circuit 751 several miles from Ginna, and had acci'dently knocked a tree into transmission wires for Circuit 751, causing it to be deenergized.

At approximately 1052 EDST, the Control Room operators entered Equipment Restoration procedure ER-ELEC.1 (Restoration of Offsite Power). The Control Room operators closed 4160 Volt circuit breaker 52/12BX to energize bus 12B from the 12B transformer at approximately 1058 EDST. At approximately 1102 EDST, safeguards buses 16 and 17 were resupplied by offsite power, via Circuit 767. (Circuit 767 continued to supply "A" train safeguards buses 14 and 18.)

At approximately 1108 EDST, September 21, 1994, the "B" Emergency D/G was stopped and realigned for auto standby.

NRC FORM 366A (5-92)

NRC FORH 366A U.S. NUCLEAR REGULATORY COMHISSION APPROVEO BY OHB NO. 3150-0104 (5-92) EXPIRES 5/31/95 ESTIHATED BURDEN PER RESPONSE TO COHPLY WITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS.

FORWARD COMMENTS REGARDIHG BURDEN ESTIHATE TO LICENSEE EVENT REPORT (LER) THE INFORMATION AND RECORDS HAHAGEHENT BRANCH TEXT CONTINUATION (MNBB 7714), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555-0001 AHD TO THE PAPERWORK REDUCTION PROJECT (3180-0104), OFFICE OF MANAGEMENT AND BUDGET WASHINGTON DC 20503.

FACILITY NAHE (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)

YEAR SEQUENTIAL REVISION Ginna Nuclear Power Plant

"'.E.

05000244 94 00 4 OF 8 012 TDT (If more space is required, use additional copies of NRC Form 366A) (17)

C. INOPERABLE STRUCTURES, COMPONENTS, OR SYSTEMS THAT CONTRIBUTED TO THE EVENT:

None D. OTHER SYSTEMS OR SECONDARY FUNCTIONS AFFECTED:

The momentary loss of power caused a loss of program memory for radiation monitor terminal RCT-1 and associated channels R-12A (Containment ventilation effluent),, R-14A (Plant ventilation ef fluent), R-31 ("A" steam line monitor), and R-32 ("B" steam line monitor).

E. METHOD OF DISCOVERY:

This event was immediately apparent due to Main Control Board alarms and indications in the Control Room when power from Circuit 751 was lost. These included Main Control Board annunciators J-7 (480 V Main or Tie Breaker Trip), L-20 (12A XFMR or 12A Bus Trouble), and L-28 (12B XFMR or Bus 12B Trouble).

F. OPERATOR ACTION:

Following the undervoltage condition on buses 16 and 17, the "B" Emergency D/G automatically started and energized these buses.

The Control Room operators immediately performed the appropriate actions and verified that the "B" Emergency D/G was operating properly, and that safeguards buses 16 and 17 were energized.

The Control Room operators restored offsite power (from Circuit 767) to buses 16 and 17, stopped the "B" Emergency D/G, and realigned it for auto standby.

Subsequently, the Shift Supervisor notified higher supervision.

The NRC was notified (at approximately 1203 EDST) per 10 CFR 50 '2 (b) (2) (ii). The NRC requested that they be notified when the cause of the event had been determined. At approximately 1243 EDST, the Shift Supervisor notified the NRC that a backhoe caused a tree to fall into transmission wires for Circuit 751.

HRC FORM 366A (5-92)

NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150.0104 (5-92) EXPIRES .5/31/95 ESTIMATED BURDEN PER RESPOHSE TO COMPLY WITH THIS INFORMATIOH COLLECTIOH REQUEST: 50 ' NRS.

FORWARD COMMEHTS REGARDIHG BURDEN ESTIMATE TO LICENSEE EVENT REPORT (LER) THE INFORMATION AND RECORDS MANAGEMENT BRANCH TEXT CONTINUATION (MNBB 7714), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555-0001 AND TO THE PAPERWORK REDUCTION PROJECT (3140-0104), OFFICE OF MANAGEMENT AND BUDGET WASHINGTON DC 20503.

FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)

YEAR SEQUENTIAL REVISION RE E. Ginna Nuclear Power Plant 05000244 5 OF 8 012 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)

G. SAFETY SYSTEM RESPONSES:

The "B" Emergency D/G automatically started due to the undervoltage condition on buses 16 and 17, displayed proper voltage and frequency and closed into safeguards buses 16 and 17 to supply emergency power.

III. CAUSE OF EVENT A. IMMEDIATE CAUSE:

The automatic actuation of the "B" Emergency D/G was due to undervoltage on safeguards buses 16 and 17.

B. INTERMEDIATE CAUSE:

The undervoltage on safeguards buses 16 and 17 was due to the loss of power from Circuit 751.

C. ROOT CAUSE:

The underlying cause of the loss of Circuit 751 was an offsite accident. A private citizen (non-RGSE employee) was operating heavy equipment and accidently knocked a tree into the transmission wires for Circuit 751. This event is NUREG-1022 Cause Code (C), External Cause. This loss of power does not meet the NUMARC 93-01, "Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants", definition of a "Maintenance Preventable Functional Failure".

HRC FORM 366A (5-92)

NRC FORM 366A U.S. NUCLEAR REGULATORY COHHISS ION APPROVEO BY OHB NO. 3150.0104 (5-92) EXPIRES 5/31/95 ESTIHATED BURDEN PER RESPONSE TO COMPLY WITH THIS IHFORHAT I ON COLLECTION REQUEST: 50. 0 HRS.

FORWARD COMMENTS REGARDING BURDEN EST IHATE TO LICENSEE EVENT REPORT (LER) THE IHFORHATION AND RECORDS MAHAGEHENT BRANCH TEXT CONTINUATION (MNBB 7714), U.S. NUCLEAR REGULATORY COHMISSION, WASHINGTON, DC 20555-0001 AND TO THE PAPERWORK REDUCTION PROJECT (3140-0104), OFFICE OF HANAGEMENT AND BUDGET WASHINGTON DC 20503.

FACILITY NAHE (1) OOCKET NUMBER (2) LER NUHBER (6) PAGE (3)

YEAR SEQUENTIAL REVISION R.E. Ginna Nuclear Power Plant 05000244 6 OF 8 94 012 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)

IV. ANALYSIS OF EVENT:

This event is reportable in accordance with 10 CFR 50.73, Licensee Event Report System, item (a) (2) (iv), which requires a report of, "any event or condition that resulted in a manual or automatic actuation of any engineered safety feature (ESF), including the reactor protection system (RPS)", in that the starting of the "B" Emergency D/G was an automatic actuation of an ESF system.

An assessment was performed considering both the safety consequences and implications of this event with the following results and conclusions:

o All reactor control and protection systems performed as designed.

o The "B" Emergency D/G operated as designed by starting and supplying emergency power to safeguards buses 16 and 17.

o Circuit 767 was still in operation supplying power to the "A" train safeguards buses; subsequently Circuit 767 was lined up to also supply power to the "B" train safeguards buses as permitted by plant technical specifications.

o Radiation monitors R-12A and R-14A are redundant to monitors R-12 and R-14. R-12 and R-14 remained operable during this event.

o Loss of radiation monitors R-31 and R-32 is compensated for by local monitoring of steam line radiation, which would be performed by plant personnel, as specified in emergency operating procedures.

Based on the above, safety was assured at all times.

it can be concluded that the public's health and HRC FORH 366A (5-92)

NRC FORH 366A U.S. NUCLEAR REGULATORY COHHISSION APPROVED BY OHB NO. 3150.0104

'5.92)

EXPIRES 5/31/95 ESTIHATED BURDEN PER RESPONSE TO COHPLY 'WITH THIS INFORHATION COLLECTIOH REQUEST: 50.0 MRS.

FORWARD COMHENTS REGARDING BURDEN ESTIMATE TO LICENSEE EVENT REPORT (LER) THE INFORHATION AND RECORDS MANAGEMENT BRANCH TEXT CONTINUATION (MNBB 7714), U.S. NUCLEAR REGULATORY COHMISSION, WASHINGTON, DC 20555-0001 AND TO THE PAPERWORK REDUCTION PROJECT (3140.0104), OFFICE OF HANAGEMENT AND BUDGET WASHINGTON DC 20503.

FACILITY NAHE (1) DOCKET NUMBER (2) LER NUHBER (6) PAGE (3)

SEQUENTIAL REVISIOH R.E. Ginna Nuclear Power Plant 05000244 YEAR 94 00 7 OF 8 012 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)

V. CORRECTIVE ACTION A. ACTION TAKEN TO RETURN AFFECTED SYSTEMS TO PRE-EVENT NORMAL STATUS:

o 'Safeguards buses 16 and 17 power supplies were restored via Circuit 767, and the "B" Emergency D/G was stopped and aligned for auto standby.

o The RCT-1 radiation monitor terminal and associated channels R-12A, R-14A, R-31, and R-32 were reprogrammed and declared operable.'.

ACTION TAKEN OR PLANNED TO PREVENT RECURRENCE:

o No corrective action is needed for the offsite accident.

o The causes and effects of loss of power to the RCT-1 radiation monitor terminal will be reviewed, to determine the need for changes in design or maintenance of the system.

VI. ADDITIONAL INFORMATION A. FAILED COMPONENTS:

None B. PREVIOUS LERs ON SIMILAR EVENTS:

A similar LER event historical search was conducted with the following results: No documentation of similar LER events with the same root cause at Ginna Nuclear Power Plant could be iden-tified. However, LERs91-002, 92-007 and 94-010 were similar events (start of a D/G due to loss of 4160 Volt bus or offsite power) with different root causes.

C. SPECIAL COMMENTS:

None NRC FORH 366A (5-92)

~ NRC FORM 366A U.S. NUCLEAR REGULATORY COHHISS ION PROVED BY OHB NO. 3150 ~ 0104 (5 92) EXPIRES 5/31/95 ESTIHATED BURDEH PER RESPONSE TO COHPLY WITH THIS IHFORHATIOH COLLECTION REQUEST: 50.0 HRS ~

FORWARD COMMENTS REGARDIHG BURDEN ESTIMATE TO LICENSEE EVENT REPORT (LER) THE IHFORHATION AND RECORDS HAHAGEMEHT BRANCH TEXT CONTINUATION (HHBB 7714), U.S. NUCLEAR REGULATORY COHMISSION, WASHINGTON, DC 20555 0001 AHD TO THE PAPERWORK REDUCTION PROJECT (31j0 0104), OFFICE OF HANAGEMEHT AND BUDGET WASHINGTON DC 20503.

FACILITY HAHE (I) DOCKET HUHBER (2) LER HUHBER (6) PAGE (3)

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