ML20073C938: Difference between revisions
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| number = ML20073C938 | | number = ML20073C938 | ||
| issue date = 04/18/1991 | | issue date = 04/18/1991 | ||
| title = Special Rept 91-04:on 910309,fire Detection Sys on Elevations 75 | | title = Special Rept 91-04:on 910309,fire Detection Sys on Elevations 75 & 95 of Reactor Bldg Made Inoperable to Facilitate Maint Activities.Fire Watch Patrol Has Been Established to Compensate for Detection Sys | ||
| author name = Barton J | | author name = Barton J | ||
| author affiliation = GENERAL PUBLIC UTILITIES CORP. | | author affiliation = GENERAL PUBLIC UTILITIES CORP. | ||
| Line 17: | Line 17: | ||
=Text= | =Text= | ||
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o-l | o-l MNuclear | ||
April 18,1991 C321-91-2093 U.S. Nuclear Regulatory Commission Attne Document Control Desk Washington, D.C. 20555 Dear Sir Subjects | :::en:r388 GPU Nuclear Corporation Forked River, New Jersey 087310388 609 971-4000 Writer's Direct Dial Number: | ||
April 18,1991 C321-91-2093 U.S. Nuclear Regulatory Commission Attne Document Control Desk Washington, D.C. | |||
20555 Dear Sir Subjects Oyster Creek Nuclear Generating Station Docket No. 50-219 Special Report No. 91-04 Enclosed is Special Report No. 91-04 which is submitted in accordance with technical specification 3.12.E. | |||
If there are any questions, please contact Mr. Michael Heller, OC Licensing Engineer at (609)971-4680. | If there are any questions, please contact Mr. Michael Heller, OC Licensing Engineer at (609)971-4680. | ||
Very t uly yours, | Very t uly yours, | ||
/ | |||
J. | J. | ||
I 9104260054 910418 ,? | Barton LD ctor Oyster Creek JJB\\MHijc cci Administrator, Region 1 Senior NRC Resident Inspector Oyster Creek NRC Project Manager i | ||
gDR | I 9104260054 910418,? | ||
gDR ADOCK0500g GPU Nuclear Corporation is a subsidiary cf General Public Utihties Corporabon | |||
..~ | |||
e' | e' Enecial Report No. 91-04 i | ||
Rcoort Dates April 18,1991 Occurrence Dates March 9, 1991. | Rcoort Dates April 18,1991 Occurrence Dates March 9, 1991. | ||
Identification of Occurrp.ngge Fire detection systems on elevations 75' and 95' of the reactor ouilding were made inoperable to facilitate maintenance activities. | Identification of Occurrp.ngge Fire detection systems on elevations 75' and 95' of the reactor ouilding were made inoperable to facilitate maintenance activities. | ||
| Line 34: | Line 36: | ||
Analysis of occurrence: | Analysis of occurrence: | ||
The isolation of the fire detection systems will prevent the receipt of automatic fire alarms from elevations 95' and 75' of the reactor building. | The isolation of the fire detection systems will prevent the receipt of automatic fire alarms from elevations 95' and 75' of the reactor building. | ||
Because the detector circuits are supervised, a break in the continuity of the circuitry will activate a trouble condition alarm. To clear this alarm, a resistot has been placed across the detector wiring terminals. This allows supervision of the balance of the system. | Because the detector circuits are supervised, a break in the continuity of the circuitry will activate a trouble condition alarm. To clear this alarm, a resistot has been placed across the detector wiring terminals. | ||
This allows supervision of the balance of the system. | |||
Corrective ActioDi To compensate for the loss of automatic fire detection capability, a fire watch patrol has been established as required by technical specification 3.12.A.2.a. | Corrective ActioDi To compensate for the loss of automatic fire detection capability, a fire watch patrol has been established as required by technical specification 3.12.A.2.a. | ||
Additionally, continuous fire watches are being provided at each cutting and welding location. Additional hand portable fire extinguishers have been provided for these fire watches. | Additionally, continuous fire watches are being provided at each cutting and welding location. Additional hand portable fire extinguishers have been provided for these fire watches. | ||
A temporary variation (TV) was prepared to control the isolation of the fire detection systems and to ensure all the systems are restored to full automatic service at the completion of the 13R refueling outage. | A temporary variation (TV) was prepared to control the isolation of the fire detection systems and to ensure all the systems are restored to full automatic service at the completion of the 13R refueling outage. | ||
(MH c3212093) | (MH c3212093) | ||
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Latest revision as of 04:00, 15 December 2024
| ML20073C938 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 04/18/1991 |
| From: | J. J. Barton GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 91-04, 91-4, C321-91-2093, NUDOCS 9104260054 | |
| Download: ML20073C938 (2) | |
Text
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o-l MNuclear
- en:r388 GPU Nuclear Corporation Forked River, New Jersey 087310388 609 971-4000 Writer's Direct Dial Number:
April 18,1991 C321-91-2093 U.S. Nuclear Regulatory Commission Attne Document Control Desk Washington, D.C.
20555 Dear Sir Subjects Oyster Creek Nuclear Generating Station Docket No. 50-219 Special Report No. 91-04 Enclosed is Special Report No. 91-04 which is submitted in accordance with technical specification 3.12.E.
If there are any questions, please contact Mr. Michael Heller, OC Licensing Engineer at (609)971-4680.
Very t uly yours,
/
J.
Barton LD ctor Oyster Creek JJB\\MHijc cci Administrator, Region 1 Senior NRC Resident Inspector Oyster Creek NRC Project Manager i
I 9104260054 910418,?
gDR ADOCK0500g GPU Nuclear Corporation is a subsidiary cf General Public Utihties Corporabon
..~
e' Enecial Report No. 91-04 i
Rcoort Dates April 18,1991 Occurrence Dates March 9, 1991.
Identification of Occurrp.ngge Fire detection systems on elevations 75' and 95' of the reactor ouilding were made inoperable to facilitate maintenance activities.
Description of Occurrences The fire detection systems were isolated by removing the detector circuit wiring connections from their control module terminal strips. This is a planned activity to prevent spurious alarms due to extensive cutting and welding in the area during the current 13R outage. We anticipate that the fire detection systems will remain isolated until the completion of the outage.
Analysis of occurrence:
The isolation of the fire detection systems will prevent the receipt of automatic fire alarms from elevations 95' and 75' of the reactor building.
Because the detector circuits are supervised, a break in the continuity of the circuitry will activate a trouble condition alarm. To clear this alarm, a resistot has been placed across the detector wiring terminals.
This allows supervision of the balance of the system.
Corrective ActioDi To compensate for the loss of automatic fire detection capability, a fire watch patrol has been established as required by technical specification 3.12.A.2.a.
Additionally, continuous fire watches are being provided at each cutting and welding location. Additional hand portable fire extinguishers have been provided for these fire watches.
A temporary variation (TV) was prepared to control the isolation of the fire detection systems and to ensure all the systems are restored to full automatic service at the completion of the 13R refueling outage.
(MH c3212093)
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