ML20006F418
| ML20006F418 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 02/09/1990 |
| From: | Keuter D SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| 90-1, 90-2, 90-3, 90-4, AGM-NUC-90-040, AGM-NUC-90-40, NUDOCS 9002280009 | |
| Download: ML20006F418 (5) | |
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SACRAMENTO MUMCIPAL UTIUTY DISTRICT D P. O. Box 16830, Sacramento CA 95852 1830,(910) 452 3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA AGM/NUC 90-040 n
o February 9, 1990
- .5 2
p U. S. Nuclear Regulatory Commission I
Attn:
J. B. Martin, Regional Administrator O
. Region V 1450 Maria Lane, Suite 210 Halnut Creek, CA 94596 L
Docket No. 50-312 1
Rancho Seco Nuclear Generating Station License No. DPR-54 SPECIAL REPORT 90-1:
FIRE BARRIERS BREACHED MORE THAN 7 DAYS SPECIAL REPORT 90-2:
FIRE BARRIERS BREACHED MORE THAN 7 DAYS SPECIAL REPORT 90-3:
FIRE SUPPRESSION MATER SYSTEN ISOLATED MORE THAN 7 DAYS SPECIAL REPORT 90-4:
FIRE BARRIERS BREACHED MORE THAN 7 DAYS
Dear Mr. Martin:
Eleven fire barrier penetrations and fire door AU-133 were not restored to operable status within the 7 days required by the Rancho Seco Technical Specifications.
The Sacramento Municipal Utility District hereby submits Special Reports 90-1, 90-2 and 90-4 in accordance with Technical Specification 3.14.6.2.
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Zone 81 water deluge system was not returned to operable status within 7 days as required by the Rancho Seco Technical Specifications.
The Sacramento Municipal Utility District hereby submits Special Report 90-3 in accordance with Technical Specification 3.14.2.2.
All fire barrier penetrations and the fire door have been returned to operable status. Compensatory measures will remain in place for Zone 81 as required by Technical Specification 3.14.6.2 until the water deluge system is returned to operable status.
C Z Q Members of your staff with questions requiring additional information or l
clarification may contact Ed Bennett at (209) 333-2935, extension 4648.
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4 Sincerely, t
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Dan R. Keuter o
Assistant General Manager
.go Nuclear
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- gg Attachment lm f
cc w/atch:
A. D'Angelo, NRC, Rancho Seco g
Document Control Desk, Washington DC YU/
m RANCHO SECO NUCLEAR GENERATING STATION O 1444o Twin Cities Road, Herald, CA 95638-9799;(209) 333 2935
[ri SPECIAL REPORT NUMBER 90-01 Fire Barriers Breached More Than 7 Days Date of Occurrence January 10, 1990 and January 16, 1990 Plant Conditions at Time of Occurrence The plant is in a defueled condition.
The reactor vessel head was placed back i
on the reactor vessel on January 19.
Installation and tensioning of the head closure studs was completed on January 30, 1990.
Identification of Occurrence Fire barrier penetrations 85/1-87aa and 334 at the 40'-0" elevation of the NSEB were not restored to operable status within the 7 days required by Rancho Seco Technical Specification 3.14.6.2.
l Description of Occurrence Penetration 85/1-87aa failed surveillance test SP.716, Refueling Interval Fire Barrier Penetrations (NSEB, 60'-0" Elevation and 40'- 0" Elevation), on January 3, 1990 due to seal degradation. On January 9, 1990 Penetration 334 also failed SP.716 due to seal degradation.
Corrective Action Taken Operability of fire detectors was verified on at least one side of the breached barriers and hourly fire watches established in accordance with Technical Specification 3.14.6.2.
These penetrations were resealed and returned to cporable status on February 2, 1990.
F.
i
' SPECIAL REPORT NtMBER 90-02 Fire Barrier Breached More Than 7 Days Date of Occurrence January 18, 1990 Plant Conditions at Time of Occurrence The plant is in a defueled condition.
The reactor vessel head was placed back on the reactor vessel on January 19.
Installation and tensioning of the head closure studs was completed on January 30, 1990.
Identification of Occurrence Fire door AU-133 (Control Room door) was not restored to operable status within the 7 days required by Rancho Seco Technical Specification 3.14.6.2.
Description of Occurrence On January 11, 1990, Fire Door AU-133 was declared inoperable when the door latch broke.
Corrective Action Taken Operability of fire detectors was verified on at least one side of the breached barriers and hourly fire watches established in accordance with Technical Specification 3.14.6.2.
The door latch was replaced and the fire I
door was r? stored to operable status on January 19, 1990.
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F l-SPECIAL REPORT NUMBER 90-03 L
fire Suppression Water System Isolated More Than 7 Days Date of Occurrence i
January 19, 1990
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Plant Conditions at Time of Occurrence The plant is in a defueled condition. The reactor vessel head was placed back l
on the reactor vessel on January 19.
Installation and tensioning of the head closure studs was completed on January 30, 1990.
Identification of Occurrence Zone 81 water deluge system for the NSEB B Cable Shaft area was not returned to operable status within 7 days as required by Technical Specification 3.14.2.2.
t Description of Occurrence The deluge system for Zone 81 was isolated on January 5, 1990 due to a false alarm associated with pressure switch PSH-99640.
Corrective Action Taken Operability of fire detectors was verified on at least one side of the breached barriers and hourly fire watches established in accordance with Technical Specification 3.14.6.2.
The cause of the false alarm will be identified and corrected and Zone 81 water deluge system returned to operable
- status, i
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P I
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f f, v SPECIAL REPORT NUMBER 90-04
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> Fire Barriers Breached More Than 7 Days Date of Occurrence January 30, 1990 and January 31, 1990 Plant Conditions at Time of Occurrence The plant is in a defueled condition.
The reactor vessel head was placed back on the reactor vessel on January 19.
Installation and tensioning of the head closure studs was completed on January 30, 1990.
L Identification of Occurrence The fire barrier penetrations in the NSEB listed below were not restored to operable status within the 7 days required by Rancho Seco Technical Specification 3.14.6.2.
Date Penetration Eenetration RSEB Elevation Eailed 77/2-75/ LAB 21'-6" 1/23/90 78/2-70AA 21'-6" 1/23/90 78/2-82AA 21'-6" 1/23/90 242 21'-6" 1/23/90 241 21'-6" 1/23/90 124 l'-6" 1/24/90 125 l'-6" l/24/90 131 l'-6" l/24/90 237 21'-6" l/24/90 Description of Occurrence The penetrations listed above failed surveillance. test SP.715, Refueling Interval fire Barrier Penetrations (NSEB, 21'-6" Elevation, l'-6" Elevation, and (-)20'-0" Elevation), due to seal degradation.
Corrective Action Taken Operability of fire detectors was verified on at least one side of the breached barriers and hourly fire watches established in accordance with Technical Specification 3.14.6.2.
These penetrations were resealed and returned to operable status on January 31, 1990.
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