Similar Documents at Cook |
|---|
|
LER-2077-019, Higher than Normal Casing Temperature of W Centrifugal Charging Pump |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 3162077019R00 - NRC Website |
|
text
NRC FORM 195 U.S. NUCLEAR REGULATORY CC SSION I2 76>=-.
lg RC DISTRIBUTION FQR PART 50 DOCKET MATERIAL DOCKET NUMBER ad-8 FILE NUMBER INCIDENT REPORT TO:
Mr., Ji G
Keppler FROM:
Indiana
& Michigan Power Company
- Bridgman, Michigan W
Jurgensen DATE OF DOCUMENT 5/12/77 DATE RECEIVED 6/8/77
~ATE R
~ORIP INAL Q COPY DESCRIPT.ION 0 NOTOR IZE D IRVNCLASSIFIED i /O'.>
PROP INPUT FORM Fn ENCLOSURE NUMBER OF COPIES RECEIVED f. s iG~<G PLANT.NAME:
Cook Unit No.
1 RJL 6/8/77 (1-P)
I Licensee Event Report (RO 50-315/77-19) on )
4/18/77 concerning the 'Wu Centrifugal.
,Charging Pump indicating higher than n'ormal-KGKNO~EDgyp gQ iyQT HZ'MO+>
(1-P)
NOTE:
IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/Jo COLLINS BRANCH CHIEF:
W 3 CYS FOR ACTION LIC, ASSTo:
- - W-. CYS ACRS /
CYS HORBRNC' FOR ACTION/INFORMATION NT Ne r INTERNALDISTRI BUTION REG 'FIL RC PDR ICE 2)
MIPC SCHROEDER/IPPOLITO HOUSTON NOVAK/CHECK GRIMES BUTLER HANAUER TEDESCO/MACCARY EISENHUT BAER
~ SHAO VOLLMER/BUNCH KREGER/J COLLINS LPDR!
TIC:
N
~
EXTERNALDISTRIBUTION CONTROL NUMBER 7716OOOOS
@ q NRC FORM 195 I2-7BI
0'
~
h
~
I V
ll
'U
pr C(i
~plcdA y><+
INDIANA& MICHIGANPDkVER CDMPANY DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 May 12, 1977 Mr. J.G.
- Keppler, Regional Director Office of Inspection and Enforcement United States Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137
Dear Mr. Keppler:
- regulatory, Docfgt Ella Operating License DPR-58 Docket No. 50-315 Pursuant to the requirements of Ap'pendix A Technical Specifications and the United States Nuclear Regulatory Commission Regulatory Guide
- 1. 16, Revision 4, Section 2.b, the following report is submitted:
RO 50-315/77-19.
Sincerely,
.W.
urg en Plant Man ger
/bab cc:
R.S.
Hunter J.E.
Dolan G.E. Lien R. Kilburn R.J. Vollen BPI K.R. Baker-RO: III R.C. Callen MPSC
'.W.
- Steketee, Esq'.
R. Walsh, Esq.
G. Charnoff, Esq.
G.
Olson J.M. Hennigan PNSRC R.S.
Keith Dir., IE (30 copies)
Dir., MIPC (3 copies)
MAY 1g l977
- .'77 gg<)00~05
' q g ~
Ir i th g
LICENSEE EVENT REPORT ~
',Form No. 4494 CONTROL BLOCK.'
[PLEASE PRINT ALLREQUIRED INFDRIVIATION]
I VFNI
~os 31 32 LICENSEE NAME LICENSE TYPE 0
4 1
1 1
1 25 26 30 LICENSE NUMBER toaj M
I 0
C C
1 0
0 0 0 0
0 0 0 14 15 REPORT REPORT CATEGORY TYPE S
7 89 DOCKET NUMBER DURDE L
0 5
0 0 3
1 5
60 61 68 [oO~]conv~
t 7
8 57 58 59 EVENT DATE REPORT DATE Q
4 1
8 7
7 0
5 1
2 7
7 69 74 75 80
EVENT DESCRIPTION
[oat Followin monthl Surveillance Testin
, the "W" Centrifu al Char ing Pump indicated 7
8 9 80 [0D3]
hi her than normal casin tern erature.
Inspection discovered a rag lodged in the re-7 89 [A@4] ~c1rculation line 60 GPM Restriction Orifice.
Attempts to ~dislodgegthe rag were un-80 7
8 9 80 K5 successful and the orifice was subse uentl re laced in kind and the um was returned 7
8 9 [oae] Lto sseerrvviice.
80 CDMPONENT MANUFACTURER P
0 2
5 47 7
8 9 80 gg ot into the system during time of rotor replacement ten days prior to this occurrence 7
8 9 PRME 80 SYSTEM
CAUSE
COMPONENT CODE CODE COMPONENT CODE SUPPLER VKILATION [onvI ~Pc
~A P
I P
E x x
~N N
7 8 9 10 11 12 17 43 44 48
CAUSE
DESCRIPTION [oa~]
The hi h tern eratures were caused b
the obstruction.
It is ver likel that the ra 7
8 9 Q1 oj even thou h ins ections had been performed.
80 7
89 FACILITY STATUS POWER OTHER STATUS Qg
~E 7
8 9
10 12 13 FORM OF ACTIVITY COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY Qg
~Z Z
NA 7
8 9
10 11 PERSONNEL EXPOSURES NUMBER TYPE OESCAIPTION
~00 0
~Z NA 7
8 9 11 12 13 PERSONNEL INJURIES NUMBER
DESCRIPTION
lI~l LQQLolnJ 7
89 11 12 OFFSITE CONSEQUENCES
@15]
NA 7
8 9 LOSS OR DAMAGE TO FACILITY TYPE
DESCRIPTION
Z NA 7
89 10 PUBLICITY QjT]
NA 7
8 9 ADDITIONAL FACTORS Qqs]
NA 7
89 METHOD OF DISCOVERY b
44 45 46 44 45 DISCOVERY DESCRIPTION LOCATION OF RELEASE fig 10 2 80 80 80 80 80 80 80 80 80 7
89 D.
G. Wizner PHONE, 616-465-5901 80 OPO 88'I ~ 887
RECEIYEO DOCONBIT PROCESSlHG VHlT err AN 7 Nt f039
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000316/LER-2077-001, Letter Reporting of Unplanned Release of Low Level Radioactive Gas | Letter Reporting of Unplanned Release of Low Level Radioactive Gas | | | 05000316/LER-2077-002, Letter Abnormal Environmental Occurrence of Total Residual Chlorine at the Condensate Outlet Exceeding the 0.10 Ppm Limit in Violation of Appendix B Technical Specifications Section 2.2.1.2 | Letter Abnormal Environmental Occurrence of Total Residual Chlorine at the Condensate Outlet Exceeding the 0.10 Ppm Limit in Violation of Appendix B Technical Specifications Section 2.2.1.2 | | | 05000316/LER-2077-003, The Inservice Residual Heat Removal (RHR) Loop Was Removed from Service for 2 Hours and 10 Minutes in Violation of Technical Specification 3.9.8 | The Inservice Residual Heat Removal (RHR) Loop Was Removed from Service for 2 Hours and 10 Minutes in Violation of Technical Specification 3.9.8 | | | 05000316/LER-2077-004, Re Failure of Cooling Coil on CPN-4 | Re Failure of Cooling Coil on CPN-4 | | | 05000316/LER-2077-005, Re Failure of 600 Volt Buses to Be Energized by Emergency Diesel Generators Due to Personnel Error & Equipment Failure | Re Failure of 600 Volt Buses to Be Energized by Emergency Diesel Generators Due to Personnel Error & Equipment Failure | | | 05000316/LER-2077-006, Concerning Hydraulic Shock & Sway Suppressor (Serial 11928) Attached to Wrong Pipe | Concerning Hydraulic Shock & Sway Suppressor (Serial 11928) Attached to Wrong Pipe | | | 05000316/LER-2077-007, Re Operation of Containment Purge & Exhaust System Without Auto-Trip Feature | Re Operation of Containment Purge & Exhaust System Without Auto-Trip Feature | | | 05000316/LER-2077-008, Re Lost of Power to Both Source Range Channels for Two Minutes During Surveillance Test | Re Lost of Power to Both Source Range Channels for Two Minutes During Surveillance Test | | | 05000316/LER-2077-009, Re Inoperable Channel of 34 Kv Blockhouse Due to Incapability to Record Event from 12/7/1976 to 13/30/1976 | Re Inoperable Channel of 34 Kv Blockhouse Due to Incapability to Record Event from 12/7/1976 to 13/30/1976 | | | 05000316/LER-2077-010, D.C Cook Unit 1 - LER 1977-010-00 Re Three Inoperable Safety Valves on Steam Generator | D.C Cook Unit 1 - LER 1977-010-00 Re Three Inoperable Safety Valves on Steam Generator | | | 05000316/LER-2077-012, Re Various Valves Not Seating Properly & LER 1977-012-00 Re Isolation Not Verified During B&C Leak Rate Test | Re Various Valves Not Seating Properly & LER 1977-012-00 Re Isolation Not Verified During B&C Leak Rate Test | | | 05000316/LER-2077-013, Re 7.5 Gallons of Boric Acid Being Injected Into RCS, Which Resulted in Tavg Decreasing 2.5 Degrees F | Re 7.5 Gallons of Boric Acid Being Injected Into RCS, Which Resulted in Tavg Decreasing 2.5 Degrees F | | | 05000316/LER-2077-015, And LER-1977-015-00 for Donald C. Cook, Unit 1 - Water Hammer Resulting in Failure of Two Seismic Snubbers, and Causing a Crack in Weld Between Auxiliary Feedwater Pipe to Second Steam Generator and a Pipe Support | And LER-1977-015-00 for Donald C. Cook, Unit 1 - Water Hammer Resulting in Failure of Two Seismic Snubbers, and Causing a Crack in Weld Between Auxiliary Feedwater Pipe to Second Steam Generator and a Pipe Support | | | 05000316/LER-2077-016, Trip of 600V AC Circuit Breaker (11D6) | Trip of 600V AC Circuit Breaker (11D6) | | | 05000316/LER-2077-017, Discovery of Inoperability of 50 Foot Wind Direction Recorder | Discovery of Inoperability of 50 Foot Wind Direction Recorder | | | 05000316/LER-2077-018, Alarms Received on All RCP Seal Flows, the Ammeter for 1W Centrifugal Charging Pump Pegged | Alarms Received on All RCP Seal Flows, the Ammeter for 1W Centrifugal Charging Pump Pegged | | | 05000316/LER-2077-019, Higher than Normal Casing Temperature of W Centrifugal Charging Pump | Higher than Normal Casing Temperature of W Centrifugal Charging Pump | | | 05000316/LER-2077-020, Breaking of East Centrifugal Charging Pump Shaft Between Third and Fourth Stage Impellers | Breaking of East Centrifugal Charging Pump Shaft Between Third and Fourth Stage Impellers | | | 05000316/LER-2077-021, Isolation Time Not Verified Following Maintenance on Third Steam Generator Sample Isolation Valve, DCR-303 | Isolation Time Not Verified Following Maintenance on Third Steam Generator Sample Isolation Valve, DCR-303 | | | 05000316/LER-2077-022, Reactor Trip and Safety Injection Due to Loss of Fourth Inverter Caused by Blown Fuse | Reactor Trip and Safety Injection Due to Loss of Fourth Inverter Caused by Blown Fuse | | | 05000316/LER-2077-023, Two Instances of Failure to Have Temporary Changes Reviewed by the Pnsrc and Approved by the Plant Manager in Violation of Appendix a Technical Specification 6.8.3.c | Two Instances of Failure to Have Temporary Changes Reviewed by the Pnsrc and Approved by the Plant Manager in Violation of Appendix a Technical Specification 6.8.3.c | | | 05000316/LER-2077-024, Electrical Failure of Valve QMO-201, Charging Header Isolation | Electrical Failure of Valve QMO-201, Charging Header Isolation | | | 05000316/LER-2077-032, And LER-1977-032-00 for Donald C. Cook, Unit 1 - Violation of Technical Specifications 3.5.4.1.b and 3.1.3.2 | And LER-1977-032-00 for Donald C. Cook, Unit 1 - Violation of Technical Specifications 3.5.4.1.b and 3.1.3.2 | | | 05000316/LER-2077-033, Position Indication for Rod F-6 Indicating a 33 Step Deviation from Bank Position | Position Indication for Rod F-6 Indicating a 33 Step Deviation from Bank Position | | | 05000316/LER-2077-034, Malfunction of Position Indication for Rods H-14 and P-8 During Exercise Required by Technical Specifications Paragraph 4.1.3.1.2 | Malfunction of Position Indication for Rods H-14 and P-8 During Exercise Required by Technical Specifications Paragraph 4.1.3.1.2 | | | 05000316/LER-2077-035, CMO-420, West CCW Heat Exchanger Motor Operated Outlet Isolation Would Not Operate Remotely | CMO-420, West CCW Heat Exchanger Motor Operated Outlet Isolation Would Not Operate Remotely | | | 05000316/LER-2077-036, Pump Failure Leading to Inoperability of Radiation Monitoring Channel R-11/12 | Pump Failure Leading to Inoperability of Radiation Monitoring Channel R-11/12 | | | 05000316/LER-2077-037, Both Trains of Control Room Pressurization Fans Were Removed from Service, in Violation of Technical Specification 3.7.5.1 | Both Trains of Control Room Pressurization Fans Were Removed from Service, in Violation of Technical Specification 3.7.5.1 | | | 05000316/LER-2077-038, Re Closure of W. CTS Heat Exchanger Inlet Valve During Routine Surveillance Test | Re Closure of W. CTS Heat Exchanger Inlet Valve During Routine Surveillance Test | | | 05000316/LER-2077-039, Re Inoperable Source Range Channels N-31 & N-32 for One Hour | Re Inoperable Source Range Channels N-31 & N-32 for One Hour | | | 05000316/LER-2077-041, Re Transformer 201CD for Unit 2 Removed from Service for Reinstallation & LER 1977-041-00 Re Control Room Pressurizer Level | Re Transformer 201CD for Unit 2 Removed from Service for Reinstallation & LER 1977-041-00 Re Control Room Pressurizer Level | | | 05000316/LER-2077-042, Re Spurious Overspeed Trip Signals from Hea Relays of Emergency Diesel Generators | Re Spurious Overspeed Trip Signals from Hea Relays of Emergency Diesel Generators | |
|