Similar Documents at Ginna |
|---|
|
LER-2076-020, For R.E. Ginna, a Accumulator Level Below Technical Specification Limit |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 2442076020R00 - NRC Website |
|
text
NRC FOAM 1 5 U.Si NUCLEAR ACGULATOAYCO IZ.7III
.NRC DISTRIBUTION FOII" PART 50 DOCKET MATERIAL ION DOCKET NUMBER 50-2/ 4 FILE'l4UMBEA INCIDEKZ REPORT J.P; O'Reilly
.I i
LETTER El ORIGINAL QCOerj 0 NOTOAIZE D ZlUNCLASSIFIEO PROP INPUT FORM FROM'ochestereCas 6 Elec.
Corp.
Rochester N.Y.
E.. D. Whit
, Jr.
DATE OF DOCUMENT 7-15-76 DATE AECEIVEO 7-g-76 NUMBER OF COPIES RECEIVED 1
DESCAIPTION Ltr.'rans the'following......
,I ENCLOSURE Li'censee event report(ROI/76-17) on 6-18-76 concerning Monitoring and Enrichment of Accumulator Boion 'Concentration;............
(1 signed cy recieved)
(2 pgs.)
ACKN0%1 KDGKD Be NOT RzMOVz
~~gmwQtaT i
' 3'iII'/~~4<<t 1PJ
'~"~- RE Ginna>,f/1 NOTE:" IP "'PERSONNEL ZXFOSURE IS INVOIIVEB~cn>~ ~
SEND DIRECTLY TO KREGER/J.COLLINS BRANCH CHIEF:
{KS..POR~ZEOM.-
IIC ~ST.:
Pur le FOR ACTION/INFORMATION CRG
' 76 SEN', TO ZA:"~
,; INTERNALDISTRIBUTION
- --NR -PDR-
- - SGHRQEDER IPPOLITO UBKlN
.NOVAK CHECK GRIMES CASE TEDESCO MACCARY EISENHUT
- - BAER-
'HAO VOLLMER BUNCH
-..KREGER J. COLLINS LPDR: 'Roc ester TIC:
EXTERNALDISTRIBUTION CONTROL NUMBER 72
r f
,1 r
4 0"'
9 ill@'~l"k'~ >!I
/, / "lj'l";
'"'OCHESTER GAS AND ELECTRIC CORPORATIO
~
~ 'tr ~
w,
'F AVENUE, ROCHES ( ER, N.Y. 14649 LEON D. WHITE. JR.
VICC I'RtSIDtRT 8" e TtI.t P v0ht ipt;sa 5JG 2700
+yA c.. /
Mr. James P. O'Reilly, Director U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, Pennsylvania 19406 Subject.
Reportable Occurrence 76-17 (30-day report), "A"Accumulator level below Technical Specification limit "R. E. Ginna Nuclear Power Plant, Unit No.
1 Docket No. 50-244
Dear Mr. O'Reilly:
In accordance with Technical Specifications, Article 6.9.2b, the attached report of Reportable Occurrence 76-17, 30-day, is hereby submitted.
Two additional copies of this letter and the attachment are enclosed.
Very truly yours, t
r tr
/
L. D. White, Jr.
Attachment cc: Dr. Ernst Volgenau (30)
Mr. William G. McDonald (3)
~.
lel,>,w,
",1
- - i
~
K l~
li (7
~
s CONTROL UCENSEE NAME [oaf N Y R
E G
7 89 4
LER 76-17/3L
~ICENSEE EVENT REPORT ~
BLOCK:
(PLEASE PRINT ALLREQUIRED INFORIVIATIONg 1
6 UCENSE EVENT LCENSE NUMBER TYPE TYPE 1
0 0 0 0
0 0
0 0 0
4 1
1 1
1 L0003~I 14 15 25 26 30 31 32 REPORT REPORT CATEGORY TYPE SOURCE DOCKET NUMBER EVENT DATE REPORT DATE Qogcoov~
~L
~L 0
6 0 0 2
4 4
0 6
1 6
7 6
0 2
1 6
2 6
7 8
57 58 59 60 61 68 69 74 75 80 EVENT OESCRIPTION uring performance of procedure S-16.11, "Monitoring and Enrichment of Accumulator 7
8 9 80 I Boron Concentration,"
"A" Accumu drain valve was opened with controls at the rear of 7
89 80
~04 ontrol board.
The operator then proceeded to front of control board to monitor level 7
8 9 80 Qpg indicators reading more conservative than those at the rear, and noted level lowered to 0
il il i
~
80 rgg~]
46%
"B" Accumulator was at proper level.
Proper (cont'd. under Additional Factors)
COMPONENT MANUFACTURER 47 7
89 PRME SYSTEM
CAUSE
COMPONENT 7
8 9 10 11 12 17 43 44 48 CAUSE OESCRIPTION toOB]
- - 16.11 did not provide precautions relative to operator remaining at valve controls 80 7 '89 80
~og during lowering level.
As recommended by PORC (meeting 75-76, item 76-932) S-16. 11 7
89
~10 as. changed to incorporate the appropriate precautions.
80 OTHER STATUS AMOUNT OF ACTIVITY OFFSITE CONSEQUENCES 7
89 FACIUTY STATUS
% POWER
@~i E
~10 O
7 8
9 10 12 13 FORM OF ACTIVITY COATENT 7
8 9
10 11 PERSONNEL EXPOSURES NUMBER TYPE
DESCRIPTION
IiioI ~00 0
E NA 7
89 11 12 13 PERSONNEL INJURIES NUMBER
DESCRIPTION
tiiol ~00 0
NA 7
89 11 12 METHOD OF DISCOVERY 44 45 46 44 45 DISCOVERY DESCRIPTION NA LOCATION OF RELEASE NA 80 60 60 7
89 LOSS OR OAMAGE TO FACILITY TYPE
DESCRIPTION
7 69 10 PUBLICITY 7
89 NA SG 60 AOOITIONAL FACTORS [ice] (cont'd. from Event Description) level was restored in 11 minutes.
Corrective Action
7
.8-9 60 Report 1081 was issued and documents the PORC-recommended actions.
(Reportable
~19 Occurrence 76-l7, 30-day).
7 89 NAME'ruce A. Snow 60 PHQNE.7 16/546-2700, ext.
29 1-2 14
'ERIC 0
4 o>>
r
~ ears.
r J
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000244/LER-2076-003, For R. E. Ginna, Residual Heat Removal System Low Pressure Piping Excessive Leakage | For R. E. Ginna, Residual Heat Removal System Low Pressure Piping Excessive Leakage | | | 05000244/LER-2076-006, Malfunction of Undervoltage Relay During Surveillance Test on 2/6/1976 | Malfunction of Undervoltage Relay During Surveillance Test on 2/6/1976 | | | 05000244/LER-2076-007, For R. E. Ginna, Concerning Relay for Train a Containment Isolation and Containment Ventilation Isolation Failure to Latch | For R. E. Ginna, Concerning Relay for Train a Containment Isolation and Containment Ventilation Isolation Failure to Latch | | | 05000244/LER-2076-008, For R. E. Ginna, Abnormal Degradation of Steam Generator Tubes | For R. E. Ginna, Abnormal Degradation of Steam Generator Tubes | | | 05000244/LER-2076-010, R. E. Ginna - Supplemental Report on LER 1976-10-00, R. E. Ginna Plant, Containment Purge Supply Valve Having Excessive Leakage During Testing | R. E. Ginna - Supplemental Report on LER 1976-10-00, R. E. Ginna Plant, Containment Purge Supply Valve Having Excessive Leakage During Testing | | | 05000244/LER-2076-011, Zero Flow Indicated for Cleanup Filtering Path in Charcoal Filter in Control Room Ventilation System | Zero Flow Indicated for Cleanup Filtering Path in Charcoal Filter in Control Room Ventilation System | | | 05000244/LER-2076-012, Containment Personnel Airlock Handwheel Shaft Seal Excessive Leakage During Testing | Containment Personnel Airlock Handwheel Shaft Seal Excessive Leakage During Testing | | | 05000244/LER-2076-013, Drop of Two Control Rods | Drop of Two Control Rods | | | 05000244/LER-2076-014, N44 Power Range Detector High Voltage Power Supply Failure | N44 Power Range Detector High Voltage Power Supply Failure | | | 05000244/LER-2076-015, Air Ejector and Blowdown Radiation Monitors Alarmed | Air Ejector and Blowdown Radiation Monitors Alarmed | | | 05000244/LER-2076-016, Rod Position Deviation Channel Was Found to Be Inoperable | Rod Position Deviation Channel Was Found to Be Inoperable | | | 05000244/LER-2076-019, For R. E. Ginna, Release of Liquid Radioactive Waste Without Continuous Operation of a Gross Activity Monitor. for R. E. Ginna, Release of Liquid Radioactive Waste Without Continuous Operation of a Gross Activity Monitor | For R. E. Ginna, Release of Liquid Radioactive Waste Without Continuous Operation of a Gross Activity Monitor. for R. E. Ginna, Release of Liquid Radioactive Waste Without Continuous Operation of a Gross Activity Monitor | | | 05000244/LER-2076-020, For R.E. Ginna, a Accumulator Level Below Technical Specification Limit | For R.E. Ginna, a Accumulator Level Below Technical Specification Limit | | | 05000244/LER-2076-021, R. E. Ginna, Unit 1, D Bank Group 2 RCCs G-3 and G-11 Partially Dropped Into Core | R. E. Ginna, Unit 1, D Bank Group 2 RCCs G-3 and G-11 Partially Dropped Into Core | | | 05000244/LER-2076-022, R. E. Ginna, Unit 1, Error in Westinghouse Safety Analysis Methods | R. E. Ginna, Unit 1, Error in Westinghouse Safety Analysis Methods | | | 05000244/LER-2076-023, R. E. Ginna, Unit 1, Incorrect Piping Installation for Modification SM 75-9.21 | R. E. Ginna, Unit 1, Incorrect Piping Installation for Modification SM 75-9.21 | | | 05000244/LER-2076-024, R. E. Ginna, Unit 1, Accumulation of Borated Water Near Valve in Safety Injection System Piping Between Boric Acid Tanks and Safety Injection Pumps | R. E. Ginna, Unit 1, Accumulation of Borated Water Near Valve in Safety Injection System Piping Between Boric Acid Tanks and Safety Injection Pumps | | | 05000244/LER-2076-025, R. E. Ginna, Unit 1, Leak at Residual Heat Removal System Return Pipe Vent | R. E. Ginna, Unit 1, Leak at Residual Heat Removal System Return Pipe Vent | | | 05000244/LER-2076-026, R. E. Ginna, Unit 1, Controller Output for Cv Spray Naoh Valve 836A Was Less than 10 Ma | R. E. Ginna, Unit 1, Controller Output for Cv Spray Naoh Valve 836A Was Less than 10 Ma | | | 05000244/LER-2076-027, R. E. Ginna, Unit 1, Liquid Leak Through Insulation on 2 Letdown Diversion Line | R. E. Ginna, Unit 1, Liquid Leak Through Insulation on 2 Letdown Diversion Line | | | 05000244/LER-2076-028, R. E. Ginna, Unit 1, on Control Rod F-12 Dropping Into Core During Operation at Reduced Load for Condenser Work | R. E. Ginna, Unit 1, on Control Rod F-12 Dropping Into Core During Operation at Reduced Load for Condenser Work | | | 05000244/LER-2076-029, R. E. Ginna, Unit 1, Core Quadrant Power Tilt Ratio Calculation in Excess of Limit During Dropped Rod Condition | R. E. Ginna, Unit 1, Core Quadrant Power Tilt Ratio Calculation in Excess of Limit During Dropped Rod Condition | | | 05000244/LER-2076-030, A Mixed Bed Demineralizer Inlet Piping Leak | A Mixed Bed Demineralizer Inlet Piping Leak | | | 05000244/LER-2076-030-03, Leak in Letdown Diversion Line on 12/16/1976, and LER 1976-030-03 a Mixed Bed Demineralizer Inlet Piping Leak | Leak in Letdown Diversion Line on 12/16/1976, and LER 1976-030-03 a Mixed Bed Demineralizer Inlet Piping Leak | |
|
